Armen Amirjanyan , Suren Bznuni Nuclear & Radiation Safety Canter (nrsc.am)
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Transcript of Armen Amirjanyan , Suren Bznuni Nuclear & Radiation Safety Canter (nrsc.am)
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Armen Amirjanyan, Suren BznuniNuclear & Radiation Safety Canter (www.nrsc.am)
Experience of NRSC on Providing Technical Support to ANRA
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CONCLUSIONS OF THE CONFERENCE:
1. The RB’s authoritative function, 2. Technical and
scientific advisory expert function. 3. …development and
maintenance of an appropriate knowledge base and associated tools …
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NRSC
Regulatory Infrastructure Model in Armenia
2. Technical and scientific advisory expert function
3. development and maintenance of an appropriate knowledge base and associated tools……and services…education and training services…national and international R&D
1. The RB’s authoritative function
ANRA
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N&RSC was established in 2002
Initial staff was 5 specialists: ◦ Thermal hydraulic analysis specialists (2)◦ Seismic and structure analysis specialist (1)◦ Systems analysis (1)◦ Support (1)
Main mission:◦ Provide technical support to ANRA.
No funding from the Government
Beginning
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Current staff: 30◦Doctors: 7 ◦PhD students: 4 ◦Engineers: 9 ◦IT specialists: 4◦Management & Administration: 6
Average age: 35
Current Staff
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StructureDirector
Deputy Director
Nuclear Safety Radiation Safety Nuclear Information
Adviser
Project Manager, QMS officer
Technological systems and components
Neutronics and Nuclear Fuel
Risk Assessment
Structural Integrity and Seismic Safety
Radioactive waste and decommissioning
Radiation Protection and Dosimetery
Nuclear information
Information technologies
Chief Accountant
Support
Thermal hydraulics
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Main capabilities
Mitigation
Confinement
Core cooling
Control of
reactivity Tools: ORIGEN, TRITON,
MONTEBURNS, KENO-VI, MCNPX, PARCS, HELIOS
Tools: RELAP5 v3.3, TRACE v5, MELCOR
v1.8.6Thermal-hydraulic,
core melting
Confinement thermal-hydraulic, hydrogen, aerosol, isotope behavior
Atmospheric dispersion, dose
calculation
Tools: MELCOR v1.8.6, COCOSYS
v2.4
Tools: RADTRAD v3.03, RASCAL
v3.0.5, PUMA v2
Isotope composition, criticality analysis, 3D
kinetics, SS core analysis , cross-sections library
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In addition…МКС-АТ6101С - γ spectrometerRadiagem-2000 - α, β, γ meterInSpector 1000 - γ, n meter, γ spectrometer.IdentiFinder –NH, γ spectrometer EBERLINE E-600, γ meterUnfors Xi – X-Ray meter, QA/QC X-ray devices.
Gamma spectrometry, X-ray testing, Individual dosimetery, Workplace monitoring, Orphan sources identification
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Cooperative Agreement between US NRC and CAMP Agreement
IAEA EC JRC GRS, Germany SERCO, UK
Development of Capabilities
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Thermal hydraulic analyses: ◦ Application of new safety
analysis methodologies: ◦ Tools:(the code and training
provided by US NRC) RELAP5 mod 3.2.2 MELCOR 1.8.5 TRACE (2009) RADTRAD
Development of Capabilities
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Development of capabilities Core Physics:
◦ Application of state-of-art methods for development of hexagonal model of VVER-440 fuel assemblies and core;
◦ Tools: ORIGEN-S, KENO-VI, PARCS-RELAP, TRITON, SCALE HELIOS TRANSURANUS
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Seismic and structural analyses: ◦ Reactor building and DG building
models development◦ Tools:
Stardyne analysis package SuperSASSI SOLVIA
Development of Capabilities
XY
Z
1
11
22
33
366
155110
120133388141
220
154
297
118
500
388
534
518479
492 680
685
772622
735
761
919
9131020
110311021095
10751100
1091
1069
10501087
10441722
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Probabilistic analyses:◦ PSA level 1 study for ANPP Unit
2: Training provided by US NRC and
IAEA.◦ Tools:
Riskspectrum
Development of Capabilities
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Development of Capabilities Radiologic measurements:
◦ Training of specialists: Environmental Radiation Monitoring (air sampling, alpha, beta
contamination); Gamma spectrometry; X-ray tasting.
◦Tools: Radiometric and dosimetric measurement equipment.
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Support to ANRA’s licensing process Support to Armenian NPP modernization
program Support to ANRA’s Radiation sources
program Support to ANRA for preparation to the new
unit licensing.
Major Activities
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Safety case study for replacement of PRZ SVs
Analysis of primary side feed and bleed operation for ANPP Unit 2
Analysis of cases potential for cold overpressurization of reactor vessel
Jet Vortex Condenser analysis
Support to ANRA
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Licensing of the ANPP Unit 2 long term operation:◦ Review of ANPP U2 Safety Analysis Report
(Selected chapters)
Licensing of Dry Spent Fuel Storage:◦ Review of Safety Analysis Report for Dry Spent
Fuel Storage (selected chapters)
Support to ANRA
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Support to ANPP Reactivity Induced
Accident were analyzed by PARCS-RELAP coupled code:
CA Ejection, Withdrawal, Drop;
Boron dilution; Incorrect connection of an
inactive loop; Inadvertent loading of a
fuel assembly into wrong position.
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Support to ANPP Seismic and structural analyses
◦ ANPP Seismic Re-Evaluation Program: Site Response Analysis; Reactor and DG buildings Floor response analysis
(reviewed by BNL) Soil and Structure Capacity Evaluation Extreme wind and snow impact assessment for
ANPP vent. stack and reactor building roof.XY
Z
XY
Z
Output Set: BODY-ZContour: Solid Z Normal Stress
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Probabilistic analyses:◦ PSA models development:
Internal IEs, Fire IEs, Flood IEs, External IEs;
◦ PSA applications: Modernisation prioritisation Training materials for ANRA newcomers; Emergency response procedures; Participation in SDP notebooks
development (with BNL); Accident scenarios development for cold
overpressure analysis.◦ Collaboration with EC JRC (ageing
PSA).
Support to ANPP
AC-3RA
Íåò ïèòàíèÿ íà 3ÐÀ ACCN-5KEN-TG3-I-EKEN-TG3-I-GKEN-TG3-II-AMore...
@AC-3RA-8
Íåò ïèòàíèÿ
@AC-3RA-9
Íåò ïèòàíèÿ îò 23Ò
ACNCBR09RO
Îòêàç âûêëþ÷àòåëÿ Â1-23Ò"À" îñòàâàòüñÿ çàêðûòûì
ACNCBR10RO
Îòêàç âûêëþ÷àòåëÿ Â2-23Ò"À" îñòàâàòüñÿ çàêðûòûì
ACNTR23THF
Îòêàç òðàíñôîðìàòîðà 23Ò îñòàâàòüñÿ â ðàáîòå
AC-T3
Íåò ïèòàíèÿ îò Ò-3
@AC-3RA-10
Íåò ðåçåðâíîãî ïèòàíèÿ
ACNCBR11GC
Îòêàç âûêëþ÷àòåëÿ Âð-3ÐÀ îò ÐÀ-2 çàêðûòüñÿ
AC-RA2
Íåò ïèòàíèÿ íà ðåçåðâíîì øèíîïðîâîäå ÐÀ-2
ACNBSA03LF
Îòêàç ñåêöèè 3ÐÀ âî âðåìÿ ðàáîòû
ACNBSA03LM
Íåãîòîâíîñòü ñåêöèè 3ÐÀ èç-çà ðåìîíòà
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Participation as a consortium member in the project for development of comprehensive safety upgrading program for ANPP◦ Basic engineering design on ECCS modernization◦ Radiological consequence analysis◦ Fire PSA◦ RIA analysis on shutdown mode
Support to ANPP
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Other Activities Database of isotopic
composition of VVER-440 fuel was developed for MELCOR model.
TRANSURANUS code subroutine TUBRP was updated to deal with hexagonal geometry of VVER-440 fuel. For that 3D Monte Carlo depletion analysis was performed by MONTEBURNS code that couples MCPX and ORIGEN codes.
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Emergency response procedures for ANRA:
MELCOR model development and analyses of severe accidents for ERC procedures development
Development of ANRA emergency response center procedures for prognoses of source terms.
Other Activities
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Radiological measurements:
◦ Workplace monitoring.◦ Individual monitoring:
Measurement and archiving of individual doses;
Tools: HARSHAW 4500 TLD. ◦ Measurements during
emergency conditions and post-emergency monitoring;
◦ Identification of unknown sources.
Other Activities
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Regulatory Documents (laws, regulations, guidelines)
Inventorization Regulatory Information System (RIS) Regional Offices Equipment Plant Decommissioning Regulatory
Licensing Plan Seminars and Trainings
Radiation Sources Program
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Action program for regulatory infrastructure upgrade
Siting safety requirement
Design safety requirements
Procedures for review of submittals
SAR structure and content requirements
New Unit Program
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What is next? • Coolant mixing in RPV – Local criticality and PTS
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What is next? Structural analyses and aging factors
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What is next? • Stress analyses of
confinement–What is the
maximum overpressure or under-pressure limit
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In Armenia technical support capabilities were created in several important areas of nuclear safety in relatively short time.
TSO provided and continue to provide essential help to RB in the areas:◦ Licensing of new facilities◦ Licensing of design changes◦ Development of regulations◦ Control of sources.
Conclusion
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All above mentioned become true because of essential help from:◦ IAEA◦ US NRC◦ GRS◦ JRC
Appreciations