Savannah River Technology Center Quarterly Report/67531/metadc684352/... · SRTC/EES/IES provided...

WSRC-TR-98-O0126

Savannah River Technology CenterQuarterly Report

JuIy, Aug., Sept., 1997

Westinghouse Savannah River CompanySavannah River SiteA:ken, SC 29808

Prepared for the U.S. Department of Energy under contract no. DE-AC09-89SR18035

DISCLAIMER

‘l%is report was prepared as an account of work sponsorti by an agency of the United StatesGovernment. Neither the United States Government nor any agency thgreof, nor any of theiremployees, makes any warranty, express or implied, or assumes any legal liability orresponsibility for the accuracy, completeness, or usefulness of any information, apparatus,produq or process disclosed, or represents that its use would not infkinge privately owned rights.Reference herein to any specific commercial produc~ process, or service by trade name,trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement,recommendation, or favoring by the United States Government or any agency thereof. Theviews and opinions of authors expressed herein do not necessarily state or reflect those of theUnited States Government or any agency thereof.

This report has been reproduced directly from the best available copy.

Available to DOE and DOE contractors horn the Oflice of Scientific and Technical Information,P.O. Box 62, Oak Ridge, TN 37831; prices available from (615) 576-8401.

Available to the public from the National Technical Information Service, U.S. Department ofCommerce, 5285 Pofi Royal Road, Springfield, VA 22161.

DISCLAIMER

Portions of this document may be illegiblein electronic image products. Images areproduced from the best available originaldocument.

WSRC-TR-98-O0126

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Savannah River Technology CenterQuarterly Report

July, Aug., Sept., 1997

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EXECUTIVESUMMARY

TRITIUM

. The Acorn Cleaning Facility hmbeenrest@ed after mincident withoil contamination in a header. No oil was found in the ACF header,associated piping nor units being cleaned.

. Three SP 981-B reservoirs were examined after one year in storageat ambient temperature. Tests were performed on the welds whichwere developed and made at the Allied Signal Kansas City Plant.Various tests, including rnicrostructural analyses, gas analyses, andburst tests were performed. The tests were required in order tofacilitate the shipment of the SP 981-B reservoirs from FederalManufacturing and Technologies to the Savannah River Site forloading.

. Tritium storage vessels with a resistance welded cap were loaded aspart of the program to develop a cap-welded seal for reclamation ofreservoirs. Storage vessels were made from forged 316L stainlesssteel in a configuration representing the first system to which the capweld may be applied. Forgings were obtained and initial test weldswere made to fabricate additional cap-welded vessels from 304L and21-6-9 stainless steel to demonstrate applicability to reservoirs otherthan the Terrazzo. A test was developed which demonstrated thatthe cap weld has sufficient impact strength.

. Recent activities have included transfer of lasers from other DOEsites to SRS to enhance development capabilities, qualification andloading of cap weld life storage samples and upgrades to the laserthat may be used for a tritium demonstration.

. SRTC/EES/lES provided daily and emergency coverage to reservoirsurveillance operations’ function test facility. IES was responsiblefor providing the fixtures, pigtails, associated hardware, electricalconnectors, and software modifications required to run over thirtyfunction tests spanning the B61, W62, W76, W78, W80, W87,Terrazzo, and Acorn units. Day-to-day support also includedsoftware support, instrumentation and calibration support, andemergency support during testing.

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. Activities in the Life Storage Program (LSP) to support DesignAgency and Tritium Operations Department needs for testing ofreservoirs continued at a high level of effort. Reports onmetallographic examination results for three SP 98 lB and a 2M

Executivesummary

Non-Acid Cleaned Reservoir were issued to the design agencies.Procedures for ultrasonic inspection of the cap plate outside thereclamation weld area of LF-7 reservoirs were approved and thirtyfive reservoirs were inspected. Five lK and five 2M reservoirs wereultrasonically inspected. Administrative activities required to close-out the corrective actions which resulted from UO TRIT-96-005 areprogressing.

. SRTC/CHTS provides program coordination and Design Lab liaisonfor the RSO mission at SRS. Recent developments include: theachievement of both the excellent and the superior levels in thePerformance Based Incentives (PBI) for the Function Test Facility;the successful test program validation of the assembly and functiontest of the gas transfer system for theB61 Stockpile Laboratory Tests(SLTS); development of a‘ function test schedule for FY98; andparticipation in the annual meeting at DOE/AL to discuss the QualityEvaluation Tracking System.

● An archival plan has been issued detailing the planned transition ofReservoir Surveillance Operations (RSO) reporting from theQUADSTAR database to the RAISIN system. The plan provides acost-effective approach to the archival task while assuring that alldata maintained by QUADSTAR are retrievable for RSO customers.Details of the plan as well as an update on the progress of reportsissued are included.

. SRTC/EES/IES provided routine and emergency support to thehydroburst facility in the areas of calibration cross-checks, tubeattachment methods, and the development of new brazing fixtures.

● SRTC is developing a process work flow model as well assupporting an Integrated Production Scheduling System Model aspart of the complex wide Enterprise Integration Modeling Program.

● SRTC/EES/IES designed, fabricated, installed, and tested areplacement pinch welder Data Acquisition and Control System forthe inert facility.

. The first HSV ever loaded has been monitored weekly during FY97.Overpressure is currently at approximately 20 torr with the HSV atapproximately 70 “C. An overpressure sample was taken andanalyzed, and w% determined to be 1005%3He. The annual isothermon a titanium sample held in the long term exposure program isbeing collected.

● SRTC/EES/IES fabricated and installed a tritium sampling systemfor the HTV shipping container.

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Executivesummary

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A request was made to increase the ordered quantity of HydrideStorage Vessels (HSV’S) with some vessel modifications made tothese lastunits. Design modifications were made, a revised drawingwas issued, and a purchase requisition change notification wasprocessed. The shipment of these latest units is expected in October.

Non-linear finite element computations and analytical modelingwere used to evaluate whether vibration modal analysis could beused to measure pressure increases in the Hydride Storage Vessel(HSV). Release of helium, formed by tritium decay, from thetitanium hydride will occur during the life of the vessel, and aconvenient non-invasive pressure indication technique would beuseful. The calculations reveal that the internal pressure from heliumrelease will not change the vibrational mode frequencies sufficientlyto be used for pressure measurement.

SRTC/EES/IES designed, fabricated, and installed an upgrade to theborescope inspection station. The system was designed to automateinspection of the fill stems, and provide for quick changeover toaccommodate any reservoir type in production without the use oftools or realignment.

SRTC/EES/IES completed design and fabrication of a new gloveboxion chamber.

SRTC/EES/IES assisted with the hardware design, fabrication,assembly, and testing of the TOPS system, a high flow rate strippersystem used during glovebox maintenance.

SRTC/EES completed design, fabrication, assembly, and testing ofthe new H1616 unpacking system which will be used to unpackH1616 shipping containers.

An experimental evaluation of plasma decontamination of tritiumcontaminated parts is underway. A commercial plasma cleaningmachine, which will be used to decontaminate tritiated parts, hasbeen set up. This process has the potential to replace several currentdecontamination practices, resulting in less waste and increasedefficiency.

SRTC/EES/lES provided routine and emergency assistance toOperations personnel for the continued operation and maintenance ofthe Container Management Facility. Areas of support includedtroubleshooting, software modifications that allow for D2 testing, thedesign and fabrication of lifting bails, and o-ring certificationassistance.

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ExecutiveSummary

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SRTC/EES/IES provided support to the loading line project in avariety of areas including software support, mechanical fixturing,instrumentation, weld development, and volume calibrations.

SRTC/EES/IES provided calibration, troubleshooting, and designsupport to the environmental chambers system.

The Environmental Conditioning stripper beds were loaded withpalladium supported on zeolite beads, Pal/z. The loading of the bedswas timed to meet the schedule for construction turnover.

SRTC/EES/D3S provided support to the design, installation,fabrication, and testing of the sample assay/vacuum bakeout system.Support included software development and testing, fabrication andtesting of the control system, specification of the heat blanket,fabrication of the hydride beds, and procurement of the cryostats.

SRTC/EES/lES provided support to the design, installation,fabrication, and testing of the function test system. Support includedsoftware development and testing, fabrication and testing of the dataacquisition system and the control system, relief valve calculations,etc.

SRTC/EES/IES completed the initial design of a hot calibrationlaboratory that will be used to recalibrate contaminated sensors.Material purchasing is in progress, and cold calibration capabilityshould be established in 723-A by October, 1997.

A hydride storage bed using passive cooling and electric heating isbeing developed for use in the SRS Tritium Projects.

SRTC/EES/IES provided significant support for the environmentalconditioning room systems.

The basic 1-D TRAC model for the entire Blanket System iscomplete and assessment of this model to LANL designspecifications under nominal and residual heat removal conditions isunderway. Modifications are being made to the existingFLOWTRAN-TF code structure to accommodate the uniquegeometrical features anticipated in the new blanket module designs.A design review has been completed and fabrication of the test loophas been initiated in the Thermal Fluids Lab (TFL) for the two-phasepressure drop test for a prototypical target rod bundle. Georgia Techhas completed all Onset of Flow Instability (OFI) experimentsincluding the effect of dissolved gases. Programmatically funded

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Executivesummary

contracts to Georgia Tech have been placed to perform single mirco-channel and seven-rod bundle target tests.

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The eighth meeting of the DOE sponsored Thermal HydraulicWorking Group (T/HWG) for the APT project was held at LANL onAugust 13’” and 14”. In support of SRTC’S APT Blanket/TargetSafety Analysis activities, the following individuals attended: LarryHarem, Zafar Qureshi (T/HWG members), Si Young Lee and FrankSmith, all from SRTC; Said Abdel-Khalik from Georgia Tech.; andJamil Khan and Curtis Rhodes from the University of South Carolina(usC).

Georgia Tech has completed all Onset of Flow Instability (OFI)experiments including the effect of dissolved gases. The CriticalHeat Flux (CHF) tests continued during June. Experiments with bothcircular and prototypical channels at different values of mass flux,pressure and inlet subcooling are being conducted.

Los Alamos National Lab (LANL) needs information on the two-phase flow - AP characteristics of an APT rod bundle. An

experiment to measure the flow-AP with a mixture of air and water atvarious flow rates has been designed and components are beingfabricated for the test apparatus. Testing is expected to begin inearly September.

Confinement and Stripping Systems for APT Tritium Processing (U),WSRC-RP-97-O0887, Rev O, was completed September 30, 1997.This report identifies functions and requirements for the tritiumprocess confinement and clean-up system (PCCS) and providessupporting technical information. for the selection and design oftritium confinement, clean-up (stripping) and recovery technologiesfor new tritium facilities in the Accelerator for the Production ofTritium (APT). The results of a survey of tritium confinement andclean-up systems for large-scale tritium handling facilities are alsopresented.

The DOE Headquarters Program Management Team for the CLWRTritium Production Program has shifted primary contractorresponsibility for program transportation activities to SRS in FY98.Packaging and transportation support to this DP-62 program will beprovided through multiple tasks led by SRS, teaming with otherdesignated sites and contractors. The program plan is beingdeveloped. Final funding levels are scheduled for definitionSeptember 15.

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ExecutiveSummary

SEPARATIONS

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Calc Note X-CLC-C-00002, Pressure Considerations for TanksContainimz Hydroxvlamine Nitrate was issued. F-Canyon tanks thatcontain or are likely to contain HAN solutions were studied. In thetanks analyzed, it was found that evaporation to the point ofinitiation of HAN decomposition would not likely result in damageto the tank.

A series of plutonium and depleted uranium (DU) co-precipitationexperiments has been completed. The results of the scoping co-precipitation experiments demonstrated that selective precipitation ofplutonium and/or DU will occur. Because of the difficulty incontrolling the solution chemistry during storage, the use of DUaddition as a soluble poison will not be pursued further.

A report entitled “Testing of Nylon Bag Material” has been issued.This report evaluates the effect of irradiation and heating on aproposed nylon bag material for plutonium cans.

Solids were received from FB-Line Tanks M34 and C7B forcharacterization. The plutonium content in solids collected fromTanks C7B and M34 has remained low; ranging from 2.3E-3 gramsPu per liter in Tank C7B to 1.4E-4 and 1.9E-4 grams Pu per liter inTank M34. At these low levels, plutonium criticality issues were notpresent.

Samples of gray and tan gasket materials were submitted forthermogravimetric analysis (TGA). Based on TGA resuks, thegasket materials are not recommended for use above 175”C.

Samples of cans and bag material were tested in the laboratory toevaluate dissolution behavior in nitric acid solutions using S,S,&Cflowsheet conditions. Both inner and outer cans rapidly dissolved inthe nitric acid solutions. The plastic bag material used to bag-out theinner cans will completely dissolve in the nitric acid solutions.

Hydrogen is generated by alpha radiolysis of water in nitric acidsolutions. There are several documents in the literature that containdata that can be used to quantify the amount of hydrogen produced,but may underestimate the hydrogen generation rates by a factor of 2to 4.

Chemical Technology personnel reviewed the August 26, 1997 draftof the EIS.

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Executivesummary

. The Mark II aqueous nitrate flowsheet developed for Complex-21 isbeing evaluated for use in stand-alone and collocated facilities.

. A supply of Np, recovered from past research efforts, was purifiedby anion exchange. It was observed that complete separation of thePa233 from the Np was not being achieved. Only 70% of the Pa233went with the waste streams in the feed effluent and wash and about30% stayed with the Np in the heart cut.

. After the existing system was evaluated opposite the effort requiredto install and start-up a new fiber-optic based calorimeter, thedecision was made to install the new instrument.

. Bench-scale experiments were conducted to study how steamcondensate mixes with and heats the TBP layer when steam passesover a TBP-nitric acid mixture. A revised report containing ananalysis of these experiments has been completed and is beingtechnically reviewed.

. The analysis of solutions containing solids and/or a second phase(organic) continues to remain an important support activity forproduct storage and process support vessels.

. Following the extended shutdown period since the last hotoperations, the quality of solvent in first uranium cycle Tank 904 hasremained very good.

. Calculations of radiolysis rates have been made for a plutonium of awide variety of isotopic compositions and moisture contents.Calculations have also been made of the recombination rate ofhydrogen and oxygen in the presence of plutonium oxide.

ENVIRONMENTAL

Environmental 3* quarter reports will be included in the 4*quarter report.

WASTE MANAGEMENT

. Rev. O of the Composite Analysis performed on the SaltstoneDisposal Facility and the E-Area Vaults (EAV) Disposal Facility(report #WSRC-RP-97-3 11) has been completed. The calculatedmaximum doses on site are well below the DOE primary dose limitof 100 mrem/year and the dose constraint of 30 mrern/year, and the

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Executivesummary

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calculated maximum collective dose to a hypothetical futurepopulation is 2.7 person-rem/year. A quantitative ALARA analysisof disposal options was not deemed necessary in this iteration of theComposite Analysis and that continued disposal of low-level wastein the Saltstone and EAV facilities.

Treatability studies on tank E-3-1 waste showed the material to bemixed waste because it displayed the characteristic of metal toxicityfor Hg and Cr and was also contaminated with low levels ofradionuclides. Cement stabilization gave a non-hazardous wasteform and was recommended for treating the five drums of the actualwaste.

Hazardous sludge drums (located in N-Area) and the waste testedhazardous per TCLP test results. TCLP testing of cement-stabilizedRinse Water Collection Tank (RWCT) sludge indicates that thesludge is not hazardous, and a recommendation has been made tostabilize the sludge by dewatering, the sludge, grouting the solid,followed by disposal in E-Area vault.

Treatment options for copper and zinc removal from the A-01effluent waste stream were evaluated as part of an on-going effort bythe SRS Environmental Compliance Group. A literature search wasperformed on possible technologies (report #WSRC-RP-97-302),and a treatability study was conducted to identify and optimize threepossible ion exchange resins to solve the Cu and Zn effluentproblem.

In late July, operation of the 2H Evaporator stopped due to solidmaterial plugging the gravity drain line. Researchers characterizedthe solid material, simulated formation in the laboratory, anddemonstrated on laboratory scale the processing of the next feedmaterial. This work allowed quick resumption of operation for theevaporator.

Extensive testing advanced the viability of electrochemical recoveryof caustic from radioactive, alkaline waste streams. Long-term (i.e.,1000 hours) durability tests at a commercial vendor locationestablish the adequacy of the materials of construction for thereactor. These tests also demonstrated the success of chemicalcleaning in the equipment as well as proving operations can takeadvantage of relatively high current densities. Local, pilot-scale testsdemonstrate that high electrical efficiency of bench-scale testspersists in larger equ~ment.streams show extremely lowcaustic stream.

Laboratory test_swith radioactive wastetransfer of contamination to the product

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ExecutiveSummary

. The safety documentation for the In-Tank Precipitation processrequires basic information on the mass transfer behavior of benzene,a byproduct of the process. Researchers used an available literaturecorrelation as well as data regression from measurements in thefacility to provide estimates of bounding mass transfer rates for. theinvolved vessels. The work also support resolution or commentsraised in Recommendation 96-1 from the Defense Nuclear FacilitySafety Board.

GENERAL

. A Modeling and Simulation Workshop was held on September 25,1997 to show the broad range of capabilities and applications usedacross the Savannah River Site to calculate the behavior of physicalsystems.

. A MOX Lead Test Assembly video was developed to support aproposal to locate a demonstration facility in existing space in H-Canyon.

. Under the Alternative Aluminum Spent Nuclear Fuel Treatment(SNF) Technology Program, an instrumented, shielded test canistersystem was developed and delivered to the 105-L assembly area on9/17/97. This met the WSRC PBI milestone.

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PROGRESS ANDACCOMPLISHMENTS

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TRITIUM

Acorn Cleaning Facilitv Support -D. L. Fkh

The Acorn Cleaning Facility has beenrestarted following an oil contaminationproblem in the exhaust header which ties inthe Acorn Cleaning Facility (ACF) with theleak test bell jars which are collocated in thesame glovebox. The source of oil wasdetermined to be coming from the exhaust ofthe He leak detector. No oil was found inthe exhaust lines to the ACF pumps nor inany of the cleaning lines. The units/systemwas verified to be essentially oil-free duringthe latest cleaning run by the use of theRGA.

All oil-contaminated lines were removedand cleaned prior to restart of the ACF.Freon rinses were used to provideverification of the extent of thecontamination. Piping changes have beencompleted to enable use of a Varian pumpfor initial evacuation of the bell jars insteadof using the He leak detector pump. Thisshould alleviate the problems causing the oilto be discharged into the exhaust header.The exhaust line has also been deeoupledfrom the common header with the AcornCleaning Facility line. Restart of the leaktest bell jars is awaiting installation ofkaowool traps on the line from thecompressor to the bell jars. The traps willbe sampled on a periodic basis for detectionof oil.

Testing of Process Prove-In SP 981-BReservoirs - E. M. Vessel

At the request of Sandia NationalLaboratory, eleven SP 981-B reservoirswere sent to the Savannah River Site to testwelds which were developed and made atthe Allied Signal Kansas City Plant. Thereservoirs were filled, stored and scheduledfor testing at prescribed intervals. Somereservoirs were filled and stored for one yearwith a mix that simulated the averagehelium concentration age at the end of itslife cycle. Others were filled with ProductSpecification MC3007A. Three reservoirswere removed after one year of storage atambient temperature and tested.

Various tests, including microstmcturalanalyses, gas analyses, and burst test wereperformed on the three reservoirs whichwere removed from storage. Isotopicprofiles based on the initial fill data andstorage conditions were also performed oneach reservoir. All evaluations of the SP981-B reservoirs found them to beacceptable after one year in storage.

Alternative Reclamation Ca~ WeldStorage Vessels - W. R. Kanne

Storage vessels with a resistance welded capwere loaded with tritium as part of theprogram to develop a cap welded seal forreclamation of reservoirs. Twelve vesselswere loaded for storage up to ten years.Vessel caps and bodies were made fromforged 3 16L stainless steel and 21-6-9stainless steel stems were projection weldedto the bodies for loading. Configuration ofthe vessels simulates the threaded boss onthe end of the reservoir for whichAlternative Reclamation is initially beingdeveloped. The resistance welded cap is thefinal step of the Alternative Reclamation

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ProgressandAccomplishments

process following laser drilling and resealingto replace the decayed tritium. Theresistance cap weld provides the primarycontainment should the laser seal leak.

Equipment to perform an impact test on thecap welds was designed and built. Theimpact test will be used to indicate thelikelihood of a cap weld failure should areservoir be inadvertently dropped. Eightcap-welded vessels that were welded usingthe present procedure were impacted withoutfailure of the cap. These included an extravessel from the set recently loaded withtritium. This vessel was impacted at themaximum machine capability. The cap,which bent about 15° but did not fail, washit near its outer end by an eight poundweight falling two feet.

Reclamation using laser welding followedby cap welding is now being considered forother systems. Storage vessels are beingfabricated from 304L and 21-6-9 stainlesssteel to demonstrate satisfactoryperformance of the cap weld for reservoirsmade from these materials. Cap materialwill remain 3 16L stainless steel. Forgingswere obtained for fabrication of thesevessels. Components for 304L vessels weremachined, Nitradd cleaned, and sampleswere welded for testing. A vessel tested tofailure burst in the cap wall, indicating highweld strength. An impact test vesselwithstood the machine maximum withoutfailure. Metallography on a third 304Lvessel and machining of 21-6-9 bodycomponents are in progress.

Alternative Reclamation of Reservoirs -S.L. West

A proposed approach for reclaimingreservoirs involves using a laser to pierce thefill stem, evacuate the reservoir, refill thereservoir and weld the drilled hole closed bydefocusing the laser. Holes so drilled are

0.005”-0.010” in diameter through the stemwall. Filler metal in the form of a sleeve canbe clipped to the stem prior to all operationsas needed to reduce the tendency forsolidification cracking in the laser weld.This process precludes the need for newreclamation hardware (1 cycle) and couldpermit reclamation in a single facility.

Two additional lasers that had been idled atother DOE sites have been brought to SRSto augment our capabilities. One is a smallNd:YAG and the other a higher powerNd:Glass laser. The NdYAG laser has beenset up in 723-A for development testing tocomplement the existing Nd:YAG laser.After characterization, this laser may bemoved to a Tritium facility for a techniquedemonstration using tritium exposedhardware. This demonstration has beenplanned for a laser in the Materials TestFacility, but thk laser is scheduled almostexclusively for use in function tests. Thelimited availability of the laser makes testingwith the new laser all the more attractive.

Additional activities have included placingcap weld samples in life storage and theprocurement of equipment to upgrade thevision system of the MTF laser. The cap isresistance upset welded over the reservoirstem to provide primary containment shouldtritium permeate through the laser weld, thatis less than through-wall. The cap weld hasbeen qualified through destructive and non-destructive tests. Samples have been tritiumfilled and placed into storage to determinethe long-term effects of exposure.

The MTF laser is being readied for areclamation demonstration should it bemade available. The upgrades include a newCCD camera, zoom lens and lighting forimproved viewing of components, and laserdiagnostics for improved repeatability. Inaddition, two focusing lasers are being testedto aid in proper remote operation.

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Function Test Facility Support -J. V. Cordaro

Instrumentation and Examination Systems(IES) provided daily and emergencycoverage to the reservoir surveillanceoperations’ function test facility. One of thesite’s Performance Based Incentives (PBIs)was the performance of thirty function testswithin this facility. IES was responsible forproviding the fixtures, pigtails, associatedhardware, electrical connectors, andsoftware modifications required to run thesethirty tests. Day to day support alsoincluded software support, instrumentationand calibration support, and emergencysupport during testing. Examples included:● completion of the installation of a newlaser positioning system.● the design and installation of an interfacebox, switches, and cables to correctproblems with current splitting in aconnector supplied by the Design Labs.s purchase of spare parts for the facility● design of a universal printed circuit boardfor the electronics● design and installation of a new dataacquisition and control system to supportTritium Function Test Facility real timemass spectroscopy research.● fabrication of a new trigger chassis. Thischassis is used to trigger the two high-speeddata acquisition hardware systems if all

interlocks have been satisfied. Alsoprovided were new high temperatureinstrumentation cables for use in the bell jar.● completed an initial evaluation of theapplicability of acoustic monitoring withinthe bell jar. Work is ongoing for installationof a system in 1998.● completed preliminary design of systemmodifications includlng laser powermeasurements, video enhancements, andimproved lighting.“ provided adjustments to the new laserpositioning control system.

● calibrated the PI amplifiers.c installed a fuse box in place of in-linefuses.● installed and tested software to correct forexcitation power supply drift.

Life Storage ProEram Activities -E. J. Majzlik, Jr.

Activities in the Life Storage Program (LSP)to support design agency and TritiumOperations needs for testing of reservoirscontinued at a high level of effort. A total ofthirteen reservoirs were unloaded for furtherprocessing. Fifty-eight new 1X, 3T, SP1101P, and Alternative Reclamationreservoirs were loaded for storage. Threereservoirs were burst tested and sixteenreservoirs were reclaimed for reloading.Sixteen reservoirs were transferred to theMaterials Test Facility for storage.Presently, an additional forty-six loadedreservoirs are awaiting transfer to theMaterials Test Facility.

Reports on metallographic examinationresults for three SP 98 lB and a 2M Non-acid Cleaned Reservoir were issued to thedesign agencies. Additionally, a report onfunction testing of a LF-7(KCP) reservoirwas issued and two annual reports for theEnhanced Surveillance Program (ESP)covering the results of ultrasonic inspectionof Life Storage Program and War Reservereservoirs were issued. This quarter, fourpapers covering the lM-97 ReclamationFeasibility Study, UT Inspection of Type21-6-9 Stainless Steel Reservoirs, TritiumCracking Model and the Life StorageProgram at the Savannah River Site,respectively, were presented at the DOEsponsored Twenty-First Aging,Compatibility and Stockpile StewardshipConference held in Albuquerque, NewMexico on September 30- October 2, 1997.

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Work to complete the Special MaterialStudy continued. Transverse metallographyof four LF-7 reservoirs progressed. Theprocedure for ultrasonic inspection of thereservoir cap plate in the area outside thereclamation weld of LF-7 reservoirs wasapproved and thirtyfive reservoirs wereinspected. Five lK and five 2M reservoirswere ultrasonically inspected. In associationwith the Special Material Study, a samplefrom the reclamation area and cap plate of a6J/2J Life Storage Program reservoir wasshipped to Los Alarnos National Laboratory(LANL) for demonstration of helium contentanalysis using new neutron bombardmentanalysis methods.

Reservoir Surveillance Operations (RSO]- S. L. Murphy

SRTC/CHTS provides program coordinationand design lab liaison for the RSO missionat SRS. Recent developments include: theachievement of both the excellent and thesuperior levels in the Performance BasedIncentives (PBI) for the Function TestFacility; the successful Test ProgramValidation of the assembly and function testof the gas transfer system for the B61Stockpile Laboratory Tests (SLTS);development of a function test schedule forFY98; and participation in the annualmeeting at DOE/AL to discuss the QualityEvaluation Tracking system.

The Function Test Facility (FTF) achievedthree significant milestones in FY97. InJulyj FT’F achieved the PBI excellent levelby completing twenty-five function tests. InSeptember, FTF achieved the PBI superiorlevel by completing 30 function tests. Alsoin September, FTF completed thirty-twofunction tests which satisfied a request byDOE/AL to reduce the function test backlogwhich resulted from a testing hiatus from thetime Mound stopped testing until testingresumed at SRS.

The B61 gas transfer system (GTS) is theseventh Stockpile Laboratory Tests (SLTS)conducted at SRS. These SLTS include:prefunction inspections, function tests, bursttesting, and post function evaluations. InJuly, the B61 Test Program Validation(TPV) was conducted by LANL of theprefunction operations in 234-H and thefunction test of the gas transfer system inFTF. After authorization to test by LANL,FTF performed function tests of the eightB61 GTS which eliminated the backlog ofB61 GTS requiring function tests.

The schedule of function tests to beperformed in FTF for FY 98 was agreedupon by SRTC and DP. The FY98 functiontest schedule includes 12 function tests and asix month outage to allow equipmentinstallation.

SRTC represented WSRC at the annualmeeting held at DOE/AL to discuss theQuality Evaluation Tracking (QET) system.The QET is administered by the WeaponsQuality Division and authorizes theStockpile Laboratory Tests. This was an allagencies meeting, and topics of discussionusually include test schedules, shipping,backlog, and any impediments to testing.

OUADSTAR / RAISIN: ReservoirSurveillance ReDortin q -W. J. Rogier

The QUADSTAR mainframe database usedfor reservoir surveillance reporting andarchival will be replaced by a more user--friendly LIMS-based database known asRAISIN. Transition from QUADSTAR to anew system is not a trivial task, with datafrom more than 1175 test entries. Toprovide a cost-effective approach toachieving this task, RSO personnel havedeveloped an archival plan which assuresthat all QUADSTAR information iselectronically archived in a reliable format

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to a dependable media (text files saved toCD-ROM), while only bringing what is byfar the most commonly examinedinformation into the new RAISIN system,all stockpile laboratory test (SLT)information from enduring stockpilesystems. This still represents a large taskwith enduring SLT tests making up 281 testentries, but compared to bringing all dataover to the new system, this represents anapproximate reduction in costs of at least50%.

A draft archival plan was provided to thedesign agencies for review and comment.Several comments were addressed withsome compromises proposed for instanceswhere differences in philosophy existedbetween LANL and SNL-CArepresentatives. A final archival plan wasissued as WSRC-CHT-97-1035 onSeptember 19.

Progress has been made on the production ofLaboratory Component Test (LCT) reportsfor the large backlog of RSO tests conductedin the FTF during FY 97. Final LCT reportsfor the two Cycle-18, W78 units were issuedon September 4. Preliminary reports forthese units were not issued since the burstand metallography (met) data needed for thefinal report were available in a timelymanner. The majority of data for Cycle-26testing of two W-62 units has been entered.Again, the preliminary report has beendeferred due to the expected availability ofburst and met data. Final LCT reports forthe W-62 is expected by the end of October.Most of the data for the five Cycle-10, W87preliminary reports has been collected. Aredesign of the W87 QUADSTAR layoutwas required for this cycle. Work on thelayout is progressing with severalmodifications underway as a result ofpreliminary data entry. The layout formatalong with sample reports will be reviewedby a design agency representative near the

end of October, with prelimina~ LCTreports soon to follow.

Hvdroburst Support -W. D. Thompson

SRTC/EES/IES provided routine support tothe Hydroburst facility as described below.

● IES provided instrumentation crosschecks to extend the calibration on the scale,Precise Sensors instrumentation, and theParoscientific transducer located in the cell.All readings were found to be acceptableand the calibrations were extended untilJyne 16, 1998.

● IES analyzed and recommendedadditional methods of attaching tubes toreservoirs.

● IES developed new brazing fixturesto support the Hydroburst process.

Enterprise Integration Modeling -J. N. Brooke

SRTC is currently developing a work flowmodel for the tritium’ processing facilities.The model uses the EXTEND modelingpackage. The Tritium Facility ExtendModel (TFEM) was written originally byLos Alamos personnel. The model has beendebugged and modified as needed tofunction reliably by SRTC personnel.Validation of the model will begin in FY98when funding is provided. Also, ananimation sub-program has been added to apart of TFEM. The animation ofprogramming will continue in FY98 whenfunding is provided.

A sub-model of the Reservoir SurveillanceOperations at SRS will be started in FY98when funding is provided. Also in FY98,the TFEM will be linked to the operationaland strategic planning work of the SRSTritium facility:

SRTC supports implementationIntegrated Production Scheduling

of theSystem

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(IPss). SRTC will provide all inputsrequired for development of the IPSS andassist in its demonstration.

WeIder DACS and ControllerReplacement - J. M. McIntosh

SRTC/EES/lES designed, fabricated,installed, and tested a replacement pinchwelder Data Acquisition and Control Systemfor the inert facility. A similar system wasalso installed in an RTF loading line withplans to also replace the system in otherloading lines in November, 1997. The weldcontroller was replaced in this loading line.The DACS controls and monitors theoperation and process parameters of theloading line pinch welders. Integratedtesting was performed on the inert and theloading line systems.

Hydride Storage Vessel (HSV) Support -K. L. Shanahan

The first HSV ever loaded (HSV-002) wastransferred to MTF for continuous pressureand temperature monitoring in FY96. Thiseffort has continued throughout FY97. TheHSV pressure has shown a slow increase,with the rate of increase dropping off withtime. Currently, the HSV temperatureremains near 70 “C, and its pressure isslightly higher than 20 torr. The gas wassampled in September, and it analyzed as100% 3He. This represents much less than1% of the total He present from tritiumdecay, indicating the titanium is retainingthe helium as expeeted.

A titanium sample with a total of 590 daystritium exposure is being analyzed. Gasoverpressure was low (

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be removed before the pressure rating isexceeded.

A method to directly measure pressureincrease in HSVS during storage withouthaving to move them (to connect to a tritiummanifold) would increase the confidence ofnot exceeding the vessel’s pressure rating, atrelatively small cost. The possibility ofusing a hammer test to perform thismeasurement was evaluated by finiteelement computation and analyticalmodeling. Inexpensive hand-held hammertest instruments are available, to easilymeasure the mechanical vibrational modesof objects (a small hammer inducesvibrations in the object, a transducer sensesthe vibrations and a portable unit presentsthe results). The hypothesis was made, thata pressure increase inside the HSV wouldalter the vibrational mode frequencies of thecontainer vessel. To evaluate thishypothesis, finite element computation andanalytical modeling were used. Both thefinite element method and the analyticalequations, when applied to the geometry ofthe HSV, agreed that the change in modefrequencies by internal pressure wasinsufficient to be used for reliable fieldhammer testing. Additional calculationsfurther showed that if the vessel were in theform of a long thin tube, the change of modefrequencies with internal pressure would bemuch greater. Based on these results, nofurther evaluation of hammer testing forHSV internal pressure measurement iswarranted.

Borescope Inspection Upzrade -J. M. Tarpley

SRTC/EES/IES designed, fabricated, andinstalled an upgrade to the borescopeinspection station. The system was designedto automate inspection of the fill stemsthrough the use of borescopes andsignificantly reduce the breakage rate of the

instruments. The system allows for quickchangeover to accommodate any reservoirtype in production without the use of toolsor realignment.

Glovebox Ion Chamber -M. B. Wood

IES completed design and fabrication of anew glovebox ion chamber. This designwill eliminate the need for backgroundreadings caused by chamber contaminationand will allow for a more accurate long termreading of glovebox atmosphere tritiumconcentration. The prototype has beeninstalled and is currently performing tocustomer satisfaction.

Tritium Oxide Portable Stripper [TOPS]- M. B. Wood

SRTC/EES/IES assisted with the hardwaredesign, fabrication, assembly, and testing ofthe TOPS system. The TOPS will be usedby Tritium operations while performingopen glovebox maintenance. The TOPS isbasically a high flow rate stripper systemthat is designed to collect tritium oxideescaping from the glovebox thus reducingstack emissions.

H1616 Unpacking Svstem -W. D. Thompson

SRTCIEES completed design, fabrication,assembly, and testing of the new H1616unpacking system which will be used tounpack H1616 shipping containers.Containers are connected to the systemwhich performs a pressure check followedby a tritium measurement. If the tritiummeasurement is below 1000 micro curies percubic meter, the operator can safety open thecontainer. The system also included a liftingtable to raise the containers to a comfortableoperating height and a packing removalsystem. Installation by Construction iscurrently in progress.

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Plasma Decontamination of TritiatedStainless Steel Parts - E. A. Clark

An unintended consequence of usingnitrogen glove boxes in the Tritium Facilityhas been the increased level of residualtritium in the glovebox atmosphere. Thishas resulted in generally higher levels ofsurface contamination of parts insidegloveboxes. Decontamination using ethanoland wipes, while effective, takes longer inthe new facility compared to older facilitieshaving one-time-flow-through air chemicalhoods. Additional waste fromdecontamination is thereby generated fromthe new facility. An alternativedecontamination process, that is faster andgenerates less waste, would be desirable. Inaddition, another decontamination processusing heated gas (nitrogen or air), used afterloading reservoirs, is being reviewed andalternative processes are being sought thatwould be faster.

Commercially available plasma cleaningmachines are being used to clean manydifferent types of materials and components.In these devices, a plasma is generated by aradio-frequency electromagnetic field in achamber containing the components, andions impact the surfaces being cleaned. Thegas that ionizes flows through the chamberat about 0.1 % of atmospheric pressure.Chemical reactions occur that would notoccur without the ionized gas, and thesurface is effectively cleaned. The wastestream is the flow of ionizing gas andmolecules created from the cleaning action,and this volume is much less than that ofconventional solvent/wipe cleaning. Aplasma cleaning machine has been installedto evaluate plasma cleaning as a method fortritium surface decontamination. Initialtesting will focus on stainless steel parts.Variables that will be tested initially includeplasma gas composition (e.g. 96% argon,

4% hydrogen or oxygen), pressure (flowrate), machine power level, and time ofdecontamination. Decontaminationeffectiveness will be evaluated using thestandard smearing and liquid scintillationcounting assay used in the SRS TritiumFacilities.

Container Mana~ement Facilitv Support -J. V. Cordaro

SRTC/EES/IES provided routine andemergency assistance to Operationspersonnel for the continued operation andmaintenance of the Container ManagementFacility. Areas of support included thefollowing:

● IES provided troubleshooting on thesource checking process andrecommended setpoint changesbased on changing roomtemperatures and humidity.

● D2 Standard - IES installed a D2standard in CMF and developed anew version of software whichallowed for D2 testing of units withthe Re-certification Leak TestSystems. Four units weresuccessfully tested at turnover.

● H1616 Container Lifting Bails - IESfabricated and load tested two liftingbails for lifting the H1616containers. The bails allow thecontainer to be safely lifted by anoverhead crane and lowered into thebelljars for leak testing.

● O-ring testing - IES providedtechnical assistance on o-ringcertification testing being performedin CMF. O-ring material used in theH16 16 containers must pass a’heliumpermeation leak test. IES executedtroubleshooting software routines onthe helium leak detector and revisedthe software to use the final heliumstandard.

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Loading Line Support - J. V. Cordaro

SRTC/EES/IES provided support to theloading line project in a variety of areasincluding software support, mechanicalfixturing, instrumentation, welddevelopment, and volume calibrations.Descriptions of support follow:Acorn Cleaning Facility

Transpector View So&are - IES wasasked to assist in loading the TranspectorView software that was ordered by BechtelDesign to run the residual gas analyzers. Bylocating some earlier versions of Labview,IES was able to run the software and installand check out in the field.

Pigtails - IES designed, fabricated, andtested pigtails.

volumes - IES designed, procured, andtested volumes for use in the ACF.Pinch Weld Fixtures - IES assisted incorrecting fill stem problems associated withthe pinch weld fixtures. IES also designedand fabricated’ pinch weld loading fixtures,nipples, and pigtails and also assistedOperations with successful pinch weldverification testing of all fixtures. Scopewas added later in the year to fabricate theunloading hardware, and that work is inprogress.Hardware - IES designed and fabricatedcutoff fixtures, x-ray fixtures, pigtail anti-rotation fixtures, calorimeter inserts,unloading inserts, holddowns, supportfixtures, support brackets, and holdingfixtures to support this loading line.Instrumentation - IES specified and orderedcontrol panel switches, deuterium andoxygen sensors, interface boxes, and flowrestrictors to support this loading line.Weld Development - IES provided welddevelopment support for the project.Examples of support include the design andinstallation of a resistance welding currentsensor.Deuterium standards - IES provideddeuterium standards, inserts, and software

changes to the Container ManagementFacility to support deuterium leak testing.Heater Socks - IES specified and orderedheater socks to support this loading line.Volume Calibrations - IES completed over60 volume calibrations associated withpiping, tanks, and fixtures of the loading lineprocess.Startup support - IES provided startupsupport in the areas of leak testing, pressuretesting, hardware support, and softwaresupport.Temporaq Calibration Man#old - IESdesigned, fabricated, tested, and delivered atemporzuy calibration manifold for use ininitial calibrations of Loading Line andAcorn Cleaning Facility instrumentation.Long Stroke Welder Estimate - EScompleted an estimate, schedule, andconstructibility review for two long strokewelders. A decision was made by thecustomer not to purchase in FY97.

Environmental Chambers Support- J. V. Cordaro.

SRTC / EES / IES provided environmentalchambers support in the following areas:

Strip Chart Recorders - IES providedtroubleshooting and calibration of the stripchart recorders associated with theenvironmental chambers data acquisitionsystem.

Calibrations - IES provided calibrationof the commercial ion chambers, pressuretransducers, Kanne air monitoring recorders,electrometers, temperature indicators,controllers, and temperature switches.

DA(X -EN designed and installed thedata acquisition and control system thatgoverned operation of the environmentalchambers.

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EC Stripper Beds Loaded with Pal/z -J. S.Holder

The Environmental Conditioning (EC)stripper beds were loaded with palladium(Pal) supported on zeolite beads, Pal/z. Theloading of the beds was timed to meet theschedule for construction turnover.Approximately 9.2 kg of Pal/z was added toeach of the six (6) stripper beds in situ (i.e.,adjacent to the EC cells and control room).The fill tubes were then welded closed byConstruction.

The Pal/z was produced on site by ETSpersonnel, who routinely synthesize thematerial for environmental monitoringapplications. Ordinarily, ETS usespalladium chloride as a starting material intheir solution deposition process. This leadsto a product with an unacceptably highchlorine content. For the seven (7) batchesof EC Pal/z, the tetraammine form ofpalladlum nitrate and a low chloride zeolitewere procured. This yielded a Pal/z productwith total chlorine well below the 250 ppmspecification.

The chlorine content of each batch wasdetermined by ADS personnel usingwavelength dispersive x-ray fluorescence(XRF); a calibration curve was generated bystandard additions of chlorine in the form ofsodium chloride. The Pd weight percent ofeach batch of the Pal/z was also determinedto meet specifications by ADS. For the Pdanalysis, energy dispersive XRF wasperformed on 50 g samples of ground andpressed Pal/z; here too, standards were madeto calibrate the apparatus.

Sample Assav/Vacuum Bakeout SvstemSup~ort -J. B. McIntosh

SRTC/EES/IES provided support to thedesign, installation, fabrication, and testing

of the sample assay vacuumSupport includedHeating Blankets - lESordered heating blanketsassay manifold.

bakeout system.

specified andfor the sample

Hydride Beds - IES designed, fabricated,and proof and leak tested the first, second,and storage hydride beds. Ancillaryhardware such as cooling water jackets andelectrical connectors were provided as well.The beds are a key element of the SampleAssay test manifold.Control System - IES designed, fabricated,tested, and installed the control system forthe new Sample Assay Vacuum BakeoutSystem. The control system will monitorand control glovebox operation. Operatingsoftware was also provided by IES.Cryostats - IES designed, specified, ordered,and tested the cryostats for the sample assaysystem.

Technical Review for Tritium FacilityModernization and Consolidation Pro.iect- A. S. Poore

A Technical Review was held bySRTC/CHTS for the Tritium FacilityModernization and Consolidation (TFM&C)Project (S-7726) on Thursday September 25,1997. There were no action items from theTechnical Review meeting.

Status of the development of new tritium gasprocessing systems was presented, whichincluded systems for process stripping,hydrogen isotope separation, and hydrogenstorage bed fabrication. Project and designstatus was also presented. Attendanceincluded Project Management, DesignEngineering, Tritium Engineering, andSRTC/CHTS.

The Process Stripper development waspresented by Joe Wermer of Los AlarnosNational Laboratory. LANL has beentasked with the development of new

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technologies for the process strippingapplication for the TFM&C project.Detailed Process Stripper meetings wereheld in the afternoon with DesignEngineering. Joe Wermer, Eric Schmeirerand Mark Whitcomb (from LANL)presented the data that has been collected todate and proposed some design options forthe Production unit. Regenerationperformance (St198 getter material)continues to be the largest unknown (andwill impact life-cycle costs). Developmentactivities, predominantly in the area of gettermaterial regeneration and life-cycle capacitydetermination, will continue throughOctober 1997.

Based on survey results from our customersand other participants, the SRTC/CHTSTechnical Review meetings for the TFM&Cproject will be held every other month tosupport the project schedule. The nextSRTC/CHTS technical review meeting willbe held in mid-November.

Function Test System SuRPort -T. R. Smail

SRTC/EES/IES provided support on thefunction test system in the following areas:High Speed Data Acquisition System - IESdesigned, fabricated, tested, and installed thehigh speed data acquisition system(HSDACS) for the new Function TestSystem. The HSDACS controls the functiontest of the gas transfer system and capturesall test data. Pressure and temperature datais recorded at up to 1000 poin~s per secondand fireset data is recorded at up to 500,000samples per second. IES designed,developed, and performed integrated testingof all control software for this system.Control System - IES designed, fabricated,tested, and installed the control system forthe new Function Test System. The controlsystem will monitor and control gloveboxoperation. Operating software was alsoprovided by IES.Belljar Repairs - IES performed leak testingon the 8001 belljar. When the initial testingwas not successful, IES recommended andassisted in making repairs to the belljarflange faces.Relief Valve Calculations for 8001 and 3501BeUjars - IES completed all calculation anddesign records that allow the use of the 8001belljar from Mound in the new FunctionTest System. Over 90 pages of calculationswere required to justify the use of eachbelljar. IES also performed the calculationsto install temporary relief valves in each ofthe belljars for purposes of leak testing.Bel~ar Feedthroughs - IES designed a set ofelectrical feedthrough connectors and proofand leak tested them. IES also providedtechnical assistance in vendor le~ testingcommercial feedthroughs.Belljar Signal Plate - IES is fabricating the8001 and 3501 belljar signal plates.800 1 Glovebox Mockup - IES completeddesign and fabrication of the 8001 gloveboxmockup for the new Function Test System.

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The mockup includes a simulated gloveboxwith glove ports and a similated 8001 belljar.B83 Mockup - IES completed design and90% of the fabrication of the B83 mockupwhich accompanies the above entry. TheB83 is the largest and most complicatedsystem to be placed in the 8001 belljar.BelZjar Hoist - IES assisted Construction inthe repair of the 800 1 belljar hoist andtroubleshooting of the 3501 belljar hoist.Internal Bell Jar Tanks - IES has designedand issued purchase requisitions for theFunction Test System internal belljar tanks.Glovebox Ion Chamber - IES designed andfabricated ion chambers associated with the8001 and 3501 belljar gloveboxes.Glovebag Design - IES has designed anddemonstrated a prototype glovebag to beused in maintenance and removal of pumpsfrom the gloveboxes. This design includesstorage and entry appendages necessary forremoving the glovebox glass and thegloveports during pump changeout. Designchanges are currently being incorporated anda purchase specification written anddeveloped to stock the items on-site.Ion Chamber - IES designed and fabricatedion chamber collimator parts.Receiver Tanks - IES designed, procured,and tested receiver tanks for the function testsystem.

Hot Calibration Laboratory SuPPort -M.B. Wood

SRTC/EES/IES completed the initial designof a hot calibration laboratory. Materialpurchasing is currently in progress. The labwill provide long term savings to Tritium byfacilitating recalibration of contaminatedsensors.

Passive Cooled Hydride Bed -E. F. Dyer

Large quantities of deuterium and tritiumwill need to be “stored on hydride beds fornew SRS Tritium Projects (TFM&C, TEF,APT). RTF hydride bed gas transfers areaccomplished by flowing large volumes ofcold or hot nitrogen through the bed’s jacketvia the RTF nitrogen systems. A ~ssivecooled and ~lectricaily Heated hydride(PACE) prototype bed is to be “cold” testedin SRTC. These full-scale tests willmeasure gas transfer rates (absorption andresorption) and compare tritiumaccountability techniques.

The PACE prototype bed consists of aninner hydride vessel (3” sch. 40 pipe)surrounded by a vacuum jacket (4” sch. 10pipe). Assembly of the bed’s inner vesselwas witnessed and photographed by EricDyer on September 2-41997. Fabrication ofthis prototype bed was completed on 9/30/97by Hydrogen Components, Inc. in Littleton,CO. The bed is expected to be received atSRS and installed in building 735-11Aduring October 1997. Modifications to theexisting hydride bed testing manifoldinclude adding two new expansion tanks(approx. 105 L each), one scroll pump, onemetal bellows pump, and at least five newrupture disks. These modifications areexpected to be completed in December1997.

Hydrogen absorption / resorption tests willstart in the 2nd Quarter of FY98. Tritiumaccountability testing will start in 3rdQuarter FY98 and the cost/ accuracy trade-off of the inventory methods tested will beevaluated. The PACE bed is expected tomeet the gas storage and transfer raterequirements for most hydride beds in theTFM&C project. If faster absorbing bedsare required in specified locations in theTFM&C project, modifications to the beddesign will be tested.

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Environmental Conditioning RoomSvstem SuDPort - J. V. Cordaro

IES completed pre-tumover testing of theMRAD drop tester which is used to exposegas transfer systems to severe shocks priorto function testing. IES assumedcompletion of the drop tester when theoriginal vendor did not have the expertise tocomplete the machine. Major realignmentalong with several major designimprovements were made to the machine,and over 600 drops were completed rangingfrom 300 g’s to 5000 g’s. Excellent pulsequality and repeatability were demonstratedfor all applicable gas transfer systems andthe Design Lab customer was satisfied withthe results of the testing. Work is ongoingto develop, fabricate, and install additionalfixtures and support hardware to support theoperation of the drop tester.

The Environmental Conditioning DACSwill control the ramp up/ramp down of thecentrifuge, all aspects of control of the droptester, and all accelerometer outputs fromthe centrifuge, drop tester and vibrationtable. Design, fabrication, and installationof the DACS were completed bySRTC/EES/IES in FY97. Softwaredevelopment was begun and will continue inFY98.

The stripper system was designed,fabricated, tested, and installed by IES. Itspurpose is to remove unwanted tritium fromthe facility in the unlikely event of a tritiumrelease during a test. After installation,external review of the radiographs of the sixstripper beds used in the stripper systemindicated that three of the beds had defectivewelds. IES worked with the vendor to repairthe welds, test, and then return the beds tothe facility and reinstall.

I13S designed, fabricated, and installed theKanne system which will assess tritium

activity levels in each of the threeenvironmental conditioning rooms. Thissystem along with the stripper system hadoriginally been specified by an engineeringcontractor. When no vendors were found toperform the work, IES was asked to assumethe system development, correct technicalerrors in the baseline, and correct thespecification that would have rendered thesystem ineffective had it been built per theoriginal specification.

IES performed initial calibrations of the fourFemtotech ion chamber monitors in the fourenvironmental conditioning rooms. Severalproblems were discovered, and IES workedwith the offsite vendor to correct thecommercial ion chamber deficiencies.

Accelerator Production of Tritium (APT]Safety Analysis Efforts for July - L. L.Harmn

Safetv Related Activities (1.191A one-dimensional blanket system modelhas been developed using the TRAC-P codeand is currently in its initial testing phase forsteady-state normal conditions. The currentmodel contains 16 unique blanket moduleswith recent additions of the snout, fourlower modules, and two upper modules.Each module is separately connected to thefixed coolant headers. The model containsabout 400 system components, including theprimary coolant loop and the residual heatremoval (RHR) systems, along withcomponent control blocks for transient Lossof Coolant Accident (LOCA) simulations.The detailed geometrical dimensions anddeposited power densities for each blanketmodule are based on existing designinformation. Hydraulic assessmentcomparing to LANL’s system designspecifications is underway for steady-statenormal operation. Additionally, headerconnection pipe sizes, piping layouts, andpump size are being updated as design

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features progress. For the Balance of Plant(BOP) components in places where noinfowation exists on the blanket side, targetsystem components are assumed. Thisversion of the system model will providetest matrix guidance, boundary conditions tolocal component models, and identificationof limiting accident scenarios forpreliminary PSAR work.

Several modifications have been made to theexisting FLOWTRAN-TF code inpreparation for modeling detailed therrnal-hydraulic behavior within the variousblanket components of the APT. Theoriginal code contained some physical andgeometric constraints specific to SRS reactorassembly modeling of two-phase flowwithin ribbed annuli. These specific modelswere removed from the fluid portion of thecode. The resulting code is now a generalhydraulic model of one dimensional two-phase flow through discrete flow channelsthat are connected to common inletioutletplenums. The coupling of the fluid thermalboundary conditions to the surrounding solidstructure was also generalized toaccommodate any solid surface. This willallow the fluid model to be coupled to adetailed three-dimensional finite elementmodel of the blanket leadhluminum solidstructures. In addition, some preliminary

plotting capabilities using TecplotTM Version7 were added to the code to display fluidvariables. The revised code has been testedby modeling two flow channels of the newBabcock & Wilcox (B&W) blanket plate-type design. Work is currently in progressto “clean up” some of the programming sothe code will be easier to maintain. SinceFLOWTRAN-TF was designed to modelair-water flows in SRS reactor assemblies, acomprehensive review is underway lookingat the constitutive models to make” sure thatthey remain appropriate for the steam waterflows expected to develop in blanket

components of the APT under accidentconditions.

Within the TFL, preparations for performingthe Ladder 2 Rod Bundle Two Phase Flowtest are in progress. Assembly of theapparatus is expected to begin the first weekin August with shake down testing beingcompleted by the end of the month. TheLadder 2 Rod Bundle Test will measurepressure drop across one rung of a Ladder 2target assembly under single/two-phase flowconditions. Test initiation activities arenearing completion and a design review onthe proposed loop has been performed. Pre-test analyses have shown that the originalrange for liquid/gas superilcial velocities isunreasonably high. Reducing/ tailoring thetest matrix to the expected range of flowconditions of concern will be resolved withLANL. The Ladder 2 rod bundle model wassupplied by LANL. Fabrication of the loopcomponents is in progress and assembly hasbegun. In response to the need foradditional high pressure pumping capacity,two additional booster pumps have beenpurchased. Informal functional tests of theloop air supply system are planned.Assembly of flow loop and supportinginstrumentation is expected to be completedin mid-August. Formal testing is expectedto begin around the end of August.

Based on the May Thermal/HydraulicWorking Group meeting, a SRTC proposalhas been submitted to LANL for thermal-hydraulic testing of a single heated rodwithin a rod bundle. This proposed testwould investigate the effects on thermalonset criteria due to potential non-idealitieswithin a rod bundle configuration. Due topresent funding constraints, this proposed’test has been placed on hold pendingapproval.

Design Related Activities (1.021

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Proposals for blanket tests have beenreceived from USC and are awaitingfunding. The structural and thermalanalysis, for design and safety purposes, ofblanket components requires information onthe interracial thermal contact (i.e., “gap”)conductance between lead components andtheir aluminum sheaths. A technical requestfor proposal was issued to USC, and hasbeen received, to measure the thermalcontact gap conductance between lead andaluminum. A Baseline Change Proposal(BCP) has been written by LANL and is inthe approval process. A test proposal formeasuring creep and thermal ratcheting inblanket components has been prepared byUSC and submitted for consideration.

Accelerator Production of Tritium (APT)Thermal Hvdrauiic Working Group - L.L. Harem

The eighth meeting of the DOE sponsoredThermal Hydraulic Working Group(T/HWG) for the APT project was held atLANL on August 13* and 14’. In support ofSRTC’S APT Blanket/Target SafetyAnalysis activities, the following individualsattended Larry Harem, Zafar Qureshi(TIHWG members), Si Young Lee andFrank Smith, all from SRTC; Said Abdel-Khalik from Georgia Tech; and Jarnil Khanand Curtis Rhodes from the University ofSouth Carolina (USC). Presentationscovered the following topics:SRTC Overview - This presentationincluded a SRTC project overview ofschedule, status of activities and keyassumptions used. The key pointhighlighted was that resolution ofoutstanding issues is essential to meeting thecurrent project schedule. A listing ofexperimental activities to date and theirstatus (i.e. proposed, in progress, completed,or canceled) was also provided.Blanket System - Status of blanket systemactivities, including a request to resolve

outstanding issues associated with theblanket system design, was presented. Moredetailed discussion included the modelingefforts for the lumped 1-D TRAC model ofthe overall system and the detailed multi-DFLOWTRAN-TF bin model. The plannedthermal gap conductance tests to beperformed at USC were also addressed.Cavity System - Recent analysis efforts toestimate counter-current flow limits withinthe gap spaces between adjacent blanketmodules were discussed and an update onnatural convection predictions under floodedcavity space conditions was provided.Target System - Recent onset of flowinstability experimental results from thesingle micro-channel test apparatus atGeorgia Tech were presented along with aupdate on several other funded tests todevelop flow regime maps within micro-channel geometries similar to the targettungsten bundles. An update on the ongoingtwo-phase pressure drop tests within aprototypical rod bundle was also presented.The LANL customer was pleased with theinformation and progress reported by SRTC.After the T/HWG meeting, a smallermeeting was held to discuss experimentalmeasurement details concerning anupcoming prototypical heated rod bundletest. Another meeting was held to discussdetails associated with the format andcontent required in the Draft PreliminarySafety Analysis Report (PSAR) along withexpected funding levels for FY98. The nextT/HWG meeting is scheduled for October.

Transportation SuPPort To TheCommercial Light Water Reactor(CLWR) Tritium Production Program -R.N. Lutz

The SRS CLWR Project Team was notifiedthat lead responsibility for most of theprogram’s transportation and packagingsupport would be shifted to SRS in FY98.A new program definition was developed,

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given previous program planning andcurrent status and schedules. The FY98program was delivered to the DP 62customer in August. DP-62 is playing anactive role in program definition. SRTCPackaging and Transportation Group (PTG)is the primary technical support organizationfor the effort. Points of contact are: CLWRProject Office, W. F. Brizes and PTG, R. N.Lutz.

Accelerator Production of Tritium (APT]ProEram -Z. H. Qureshi

Georgia Institute of Technology (GIT) iscontinuing to perform Onset of FlowInstability/Critical Heat Flux (OFI/CHF)testing of a single micro-channel includingthe effect of dissolved gases, and a model topredict OFI is now being developed.Experiments with both circular andprototypical micro-channels at differentvalues of mass flux, pressure and inlet sub-cooling are being conducted. Tests are beingconducted with a large bypass in parallel tothe heated test section to simulate actualAPT design flow passages and future testswill be conducted without any bypass flow.The ongoing OFI/CHF testing by GITwithin single micro-channels confirmsearlier expectations based on FLOWTRAN-DF calculations that, over the expectedrange of conditions, flow instability of the“Ledinegg” type will be a more limitingthermal criterion than traditional CHF.These preliminary calculations performedduring the summer of FY96 were the resultof available literature based correlations.New correlations based upon the morerecent micro-channel data will be developed.An impact on existing design margins isanticipated, although the magnitude of thisimpact is unknown at this time due tovarious factors such as operating level ofdissolved gases within the primary coolantthat are yet to be determined.

In addition to the OFI/CHF tests, LANLidentified the need for a two-phase flowregime map and single-phase convectiveheat transfer data appropriate for the APTbundle design and flow conditions.Consequently, the original GIT contract wasrevised to reflect this additional work scope.In response, GIT has designed andconstructed an experimental facility todetermine two-phase flow regimes in singlemicro-channels. Additionally, two-phasepressure drop will also be measured forcircular and triangular test sections. GITalso responded to a technical request forproposal to perform a seven-rod flow regimemap test and funding for this test through aBaseline Change Proposal (BCP) by LANLhas occurred.

Accelerator Production of Tritium (APT]Ladder 2 Rod Bundle Two-PhaseHvdraulic F1OWTest -T. J. Steeper

Air and water will be mixed just ahead ofthe tube sheet in a mockup of the targetladder 2 rod bundle provided by Los AlamosNational Laboratory. Flow rates andpressures will be measured to map out flowversus pressure drop under two phase flowconditions. Design and componentmachining have been completed.Preparation of the work package coveringwelding procedures and inspections iscomplete. The air injector was fabricated atan offsite machine shop, and has beenreceived. Final loop assembly has beenstarted in the Thermal Fluids Laboratory.

APT Confinement Svstem Study - R. H.Hsu

Confinement and Stripping Systems for APTTritium Processing (U), WSRC-RP-97-00887, Rev O, was completed September 30,1997. This report identifies functions andrequirements for the tritium processconfinement and clean-up system (PCCS)

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and provides supporting technicalinformation for the selection and design oftritium confinement, clean-up (stripping)and recovery technologies for new tritiumfacilities in the Accelerator for theProduction of Tritium (APT). The results ofa survey of tritium confinement and clean-up systems for large-scale tritium handlingfacilities are also presented.

The authors recommend that APT tritiumprocessing equipment be confined ingloveboxes, or secondary jackets, in keepingwiti, current SRS practice and As Low AsReasonably Achievable principles.Stripping of the glovebox atmosphere gas isrecommended to be on a as-needed basis,when triggered by high tritium, oxygen, ormoisture level. Glovebox pressure shouldbe negative unless very lowoxygen/moisture concentrations are requiredby the process. The PCCS stripper systemmay be located outside of gloveboxconfinement, if justified by tritiuminventory, dose and risk considerations.

Based on the conceptual APT process withseveral water loops, large-scale equipmentand susceptibility of confinement system toair/moisture intrusion, and anticipated sitingof the APT at the SRS, the recommendedstripper technology is the conventionaloxidation-absorption process. Theadvantages of the oxidation-absorptionprocess over getter technology includeproven performance, high efficiency, androbustness to handle air/moisture conditions.Getter technology does not generate tritiatedwater, but requires a sacrificial getter toremove oxygen and crack water. A getterprocess will always generate more sacrificialwaste beds than the conventional z bedrecovery process using Mg or U beds.

No recommendation was made on thepreferred tritium recovery technology fromtritiated water. It is recommended that R &

D continue on technologies that may replacethe conventional Mg or U water crackingprocess: solid oxide electrolysis technologyat SRS and the palladium membrane reactor(PMR) technology at LANL.

Remote Handling Development - JimWong

A computer simulation of changeout of atarget module in the new single targetsystem has been developed. This simulationincludes a revised jumper layout that reflectsa reduction in the number of jumpers andtotally remote changeout of the module.The simulation demonstrates the entireprocess for changing out a target moduleincluding 3He connector operation andwater jumper operation. The simulation wascompleted on September 30, meeting amilestone on schedule.

The 3He lines to and from the modules inthe targethlanket vessel will be jacketed toallow detection of a 3He leak andcontainment of the leak. This will requireunique, jacketed 3He jumpers.Development of a connector for thesejumpers is underway. This developmentincludes design, fabrication and testing ofthe connector and the remote tools to operatethe connector. Two alternative designs forthe threaded coupling to compress the 3Heseal were fabricated and tested. Eachcoupling worked well at the small anglesthat will be produced by the alignment pins.The shorter coupling was selected for theconnector to reduce the height of the innerassembly. The inner connector wascompleted on September 29, meeting amilestone on schedule. The remote tool foroperating the inner coupling was completedon September 30, meeting a milestone onschedule.

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Commercial Light Water ReactorTritium Extraction Facility (TEF) -Malcolm Kyle

The TEF is a new facility being designed toprocess tritium targets which will beirradiated in a commercial nuclear reactor.SRTC is providing development support inseveral areas. Details are provided forindividual development tasks below:

Infrastructure (Task 1) - The project teamhas selected 777-1OA as the preferred sitefor the Development and Test Facility(DTF). A detailed cost estimate for therenovation of this facility was generated byPE&C personnel. A subsequent meetingwas held between project team personneland PE&C personnel to ensure that therewas agreement on the scope of the estimate.

Major Modules (Task 2) - RSE isprogressing on the detailed design of thehoist section of the transport module. Theseal section of this module is being sentoffsite for fabrication. A stand is beingdesigned to support the active portion of thedouble door seal. This stand will simulatethe upper portion of the stationaryprocessing modules.

Seals and Connectors (Task 3) - Pneumaticactuators for the double door seal are onorder. A pneumatic clamping system thatsecures the transport module seal section tothe fixed module seal section has beenselected. Pneumatic control valves havealso been’ selected which will allow forcontrol of individual components and alsoprovide for remote operation. A preliminarypiping system design drawing for thepneumatic double door controls has beendeveloped.

Pump Train Development (Task 5) - Workcontinued on the P&ID to define themockup piping/pumping system that will be

installed in the DTF. Work was alsoperformed to determine the extractionfurnace void volume for sizing of thesimulated furnace tank. Based on an 18“O.D., 20-4” high primary containmentfurnace (975 liters) and a basket volume (notoccupied by gas) of 171 liters, a“tank of 804liters (28.4 cubic feet) is needed to simulatethe furnace volume. This equates to a 36”O.D. tank roughly 4’ high.

A proposed piping/pumping system test planhas been developed. It includes series oftests beginning with individual componenttesting and evolving into testing of a fullsystem mockup in the DTF. The remainingthree metal bellows pumps that were orderedhave been received. Also, three Norrnatexscroll pumps have been withdrawn fromExtra Machinery. A fourth pump wasordered from the manufacturer and willarrive early in CY98.

Program General - As part of the componentdevelopment task, EES has been supportingTEF Design personnel on the developmentof the furnace basket, extraction lid,overpack, and stationary modules. Relatedefforts in this area include conceptual designof a basket grapple and individual rodhandling technology. Due to overpack andfurnace clearances, the lift-from-lid concepthas been selected over the O.D. basketlifting approach. Lid lifting introduces astructural lid and structural seal interface.SRTC is providing technical support in eachof these areas. Conceptual designs for thelifting lid and lifting fixture (grapple) arecurrently being developed.

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SEPARATIONS

Hvdroxvlamine Nitrate Storage and Use- M. E. Hodges, J. E. Laurina~ and T. S.

Rudisill

A tank at Hanford, containing a solution ofhydroxylamine nitrate (HAN) and nitricacid, ruptured on May 14, 1997 as a result ofthe autocatalytic decomposition of the HAN.The solution had been in the tank for aboutfour years, during which time, most of thewater had evaporated, leaving a concentratedsolution of HAN and nitric acid. HAN isvery stable in nitric acid solution until theacidity and HAN concentrations approach2.5M. At higher concentrations, dependingon temperature and dissolved iron, anautocatalytic decomposition can occur,releasing large amounts of N20 gas but little

heat. HAN is used as a reductant in thesecond plutonium cycle of the PUREXprocess. In the first solvent extraction cycle,a solution of HAN and ferrous sulfarnate(FS) in dilute nitric acid was used untilrecently to reduce Pu to the inextractablePu(HI) state. F-Canyon personnel requestedthat we investigate the possibility of areaction at SRS similar to that at Hanford.

Calc Note X-CLC-C-00002, PressureConsiderations for Tanks ContainingHYdroxvlamine Nitrate was issued. The F-Canyon tanks that contain or are likely tocontain HAN solutions were studied. Twoscenarios were assumed. In the first case,the solutions were allowed to evaporate until”the HAN and nitric acid solutions reachedautocatalytic decomposition conditions. Thepressures resulting from the N20 and water

vapor produced were then calculated. In thetanks analyzed, evaporation to the point ofinitiation would not likely result in damageto the tank. In the second case, it wasassumed that concentrated nitric acid wassuddenly added to a full tank of HANsolution. In this scenario, except for one

border-line case, the tank vents appearadequate to prevent excessive pressureincrease.

Co-precipitation of Plutonium andUranium - J. H. Gray, P. A. Westover

A series of plutonium and depleted uranium(DU) co-precipitation experiments has beencompleted. The objective was to verify thatselective precipitation would not be aproblem during interim storage inunderground waste tanks. To demonstratethis objective, DU was added to a plutoniumsolution at a 220 gram DU to 0.60 gramplutonium ratio and precipitates wereformed by addition of sodium hydroxide(NaOH), phosphoric acid (H3P04), and

dibutyl phosphate (DBP).

The results of the scoping co-precipitationexperiments demonstrated that selectiveprecipitation of plutonium and/or DU willoccur. Because of the difficulty incontrolling the solution chemistry duringstorage, the use of DU addition as a solublepoison will not be pursued further.

The addition of NaOH, H3P04, and DBP

was made to acidic solutions, about onemolar nitric acid, and to more neutralsolutions, in the pH range from 2-4. Theaddition of NaOH resulted in precipitationof plutonium hydroxide and sodiumdiuranate. The addition of DBP precipitatedPu-DBP compounds, but no uranium. Theaddition of H3P04 precipitated both

plutonium and uranium phosphates in theacidic solution, but no plutonium from thepH 2-4 solution.

Nylon Bag Material Testirm (U) - J. E.Laurinat

Currently, low density polyethylene (LDPE)and polyvinyl chloride (PVC) bags are used

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to bag out cans of plutonium-bearingmaterial for transfer to F-Canyon for furtherprocessing. Because LDPE and PVC are notsoluble in the nitric acid dissolver solutionused in F-Canyon, the cans of material mustbe repackaged before they are added to thedissolver. Nylon is soluble in nitric acid, sosubstitution of nylon for LDPE or PVC willallow these items to be packaged usingnormal practices and charged directly to thedissolver.

A report entitled “Testing of Nylon BagMaterial” has been issued. This reportevaluates the effect of irradiation andheating on a proposed nylon bag material forplutonium cans. This material is beingconsidered as a replacement for the currentlyused polyethylene and PVC materials. Thereport concludes that over the expectedservice lifetime the nylon bag material willbe satisfactory.

Characterization of FB-Line Tank Solids- J. H. Gray, K. J. Kalbaugh

Recently solids were received from FB-LineTanks M34 and C7B for characterization.Tank M34 is the recycle feed tank whichcollects plutonium solutions that arerecycled back to F-Canyon. Tank C7B is acation product hold tank which containsconcentrated plutonium solutions. Thereasons for characterization of these solidsinclude determination of the plutoniumcontent and identification of elements andcompounds present.

The plutonium content in solids collectedfrom Tanks C7B and M34 has remainedlow; ranging from 2.3E-3 grams Pu per literin Tank C7B to 1.4E-4 and 1.9E-4 grams Puper liter in Tank M34. At these low levels,plutonium criticality issues were not present.

Most of the solids are typical Fe, Cr, Nicorrosion products, K-Al-silicate muscovite

clay, silicon compounds, and smallerconcentrations of Zr, W, Ti, and Sn. No Pu-phosphorus or Pu-sulfur compounds werepresent. Effort is underway to identify whatform of plutonium is present.

Testiw of Pu Can Gasket Material -J. E. Laurinat, J. W. Congdon

Separations requested that the gasketmaterial used to seal the lids of plutonium“food pack” cans be tested for service atelevated temperatures.

Samples of gray and tan gasket materialswere submitted for thermogravimetricanalysis (TGA). The TGA samples wereheated under both air and argonatmospheres. The tests with air showed thatboth types of gasket material began tooxidize at approximately 175”C, asevidenced by a small weight gain. Based onthese results, the gasket materials are notrecommended for use above thistemperature.

Dissolution of Sand. Slag. and CrucibleRepackaging Cans - J. H. Gray, P. A.Westover

During solvent extraction operations, thepresence of insoluble organic material at theorganic-aqueous interface could cause phasedisengaging problems. Two sources ofinsoluble organics are the plastic coating oncans used to repackage sand, slag, andcrucible (S, S,&C) material and the plasticbags used to encapsulate inner cans. Toeliminate these sources, the inner cans weresandblasted, the outer cans manufacturedwithout a plastic coating, and a solubleorganic bag material selected for therepackaging operations. Samples of thesecans and bag material were then tested in thelaboratory to evaluate dissolution behaviorin nitric acid solutions using S,S,&Cflowsheet conditions.

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Both inner and outer cans rapidly dissolvedin the nitric acid solutions. The dksolvingreaction is exothermic, generates brownfumes, and consumes 0.054 moles of HN03

per gram of material dissolved.

The plastic bag material used to bag-out theinner cans will completely dissolve in thenitric acid solutions. The only remainingundissolved organic materials were theorganic rings used as seals on the innersurface of both lids. These organic ringswill remain undissolved and contribute 0.13and 0.32 grams of organic residue per innerand outer can lid, respectively. However,this small amount of organic materialremaining undissolved should have anegligible effect on subsequent solventextraction operations.

Hydrogen Generation by AlohaRadiolysis of Nitrate Solutions - E. A.Kyser and J. W. McC1ard

Hydrogen is generated by alpha radiolysis ofwater in nitric acid solutions. When analpha particle strikes a molecule of water ornitric acid, alpha fragmentation products(both radicals and ions) are formed. Thesefragments react with other fragments andions to form molecules and other ionicspecies. Hydrogen gas buildup in tanks overPu solutions is controlled to preventformation of fiammable gas concentrations.The presence of oxidizing or reducingagents shifts the equilibrium of thecompeting reactions. This modifies theamount of hydrogen and oxygen that areproduced, but the total nitrate concentrationpredominately determines the hydrogenproduction in nitric acid systems. There areseveral documents in the literature thatcontain data that can be used to quantify theamount of hydrogen produced, but mayunderestimate the hydrogen generation ratesby a factor of 2 to 4.

Several of the sources of data on this subjectwritten prior to 1992 indicate that thehydrogen generation rate for Pu239-nitricacid solutions is significantly lower than forPo21O and Cm244. It was not recognized atthe time that, because of the preparationtechnique for the test solutions, significantlymore total nitrate was present than just fromthe nitric acid. This means that thehydrogen generation rates wereunderestimated for any given total nitrateconcentration. In the last several years ourunderstanding of the differences between thevarious radiolysis data for Pu239, Po21O andCm244 in nitric acid solutions in theliterature has greatly improved. We nowrecognize that the hydrogen generation ratesfrom these different sources of data are infairly good agreement when the additionalnitrate from Pu nitrate is accounted for.Alpha radiation in nitric acid solutiongenerates the same amount of hydrogen(scaled on aIpha energy) without regard tothe parent isotope.

Support for Residue EnvironmentalImpact Statement - A.M. Murray

The Department of Energy is developing anEnvironmental Impact Statement (EIS) forthe processing of residues. Severaltechnologies are being considered for eachresidue stream and different sites are beingevaluated for the actual processing. Theoptions include the current baseline plans,technologies that only stabilize the residuesfor interim storage, and technologies thatseparate the actinides from the residuematrix so that the bulk material meets theSafeguards Termination Limits (STL) fordisposal at the Waste Isolation Pilot Plant.The EIS is being prepared by ScienceApplications International Corporation(SAIC) personnel. At the request of NMPPrograms, Chemical Technology personnel

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have reviewed different sections of theSAIC draft.

Chemical Technology personnel reviewedthe August 26, 1997 draft of the EIS. Thereview focused on the Introduction,Proposed Action and Alternatives Chapter,Appendix B (Plutonium Residues and Scruballoy

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