By R.K. Choudhury (CSI), S. Ganesan, A. Saxena, B.K. Nayak, R.G. Thomas, Devesh Raj, Anek Kumar and...

Discussion of Research Proposal and Expected outputs Benchmark Performance

TITLE OF RESEARCH CONTRACT PROPOSAL:Experimental and theoretical investigations on prompt neutron

spectra and their angular distributions for selected major and minor actinides

Part of new IAEA CRP:“Prompt fission neutron spectra of actinide nuclei”, IAEA-NDS

ByR.K. Choudhury (CSI), S. Ganesan, A. Saxena, B.K. Nayak, R.G.

Thomas, Devesh Raj, Anek Kumar and H.Naik Bhabha Atomic Research Centre, Trombay, Mumbai-400085 INDIA

1st Research Coordination meeting on “Prompt Fission Neutron Spectra of Actinides”,

6-9 April 2010, IAEA Headquarters, Vienna, Austria.

A new IAEA CRP:“Prompt fission neutron spectra of actinide nuclei”, IAEA-NDS

TITLE OF RESEARCH CONTRACT PROPOSAL:Experimental and theoretical investigations on prompt neutron spectra and their angular distributions for

selected major and minor actinides

1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna


Presented by Prof. S. Ganesan

Head, Nuclear Data Section, Reactor Physics Design Division& Professor, Homi Bhabha National Institute, Mumbai, DAE

5th Floor, Central Complex,Bhabha Atomic Research Centre, Trombay, Mumbai-400085 INDIA

Email: [email protected] [email protected]

mailto:[email protected]

mailto:[email protected]

NUCLEAR DATA ACTIVITIES IN INDIA

• Basic nuclear data physics measurements. FOTIA (BARC), BARC-TIFR Pelletron, PURNIMA (BARC) D-D, D-T sources), Photon induced reactions (Electron accelerator based bremstrahlung at Kharghar); Pune 14 MeV facility. IPR 14 MeV facility

• New facilities for data measurements (being discussed)• EXFOR compilations. Three successful workshops thus far: 2006

(Mumbai) , 2007 (Mumbai) , 2009 (Jaipur)• Nuclear model based calculations. E.g., EMPIRE, TALYS• Processing of evaluated nuclear data files to produce plug-in libraries

for discrete ordinates and Monte Carlo codes. NJOY (USA) equivalent to be developed

• Efforts to digest the status of covariance error methodology in nuclear data and its applications. A beginning with a DAE-BRNS Project at Manipal

• Preparation of integral Indian experimental criticality benchmarks for integral nuclear data validation studies. (KAMINI, PURNIMA-II benchmarks completed and accepted by the US-DOE). PURNIMA-I benchmarking in progress. Reactor sensitivity studies –AHWR, CHTR (RPDD, BARC)

Indian nuclear data mirror website at Mumbai

http://www-nds.indcentre.org.in

INTERNET

IAEA Main Server in Vienna

Public Client

NDS Mirror Site in INDIA

IAEA NDS MIRROR SITE SET-UP

www-nds.indcentre.org.in

2Mbps Link

www-nds.iaea.org

Daily Updates

The online nuclear data services (http://www-nds.indcentre.org.in/)

mirror the nuclear data website of the Nuclear

Data Section of the International Atomic

Energy Agency (IAEA), Vienna (http://www-

nds.iaea.org).

The MOU between DAE/BARC and the IAEA

is expected to be continued beyond 2010.

Under this arrangement, online-updating every 12 hours is performed in the mirror with the IAEA website through a 2MB direct link. The server is being maintained by BARC Computer Division - with manpower and machinery. It offers 2-3 times faster downloads in BARC compared to the Vienna site. India offers to collaborate with other network of reaction data centres and help in promoting the online nuclear data services in the coming years.

19 March 2010

NATIONAL THEME WORKSHOP ON NUCLEAR REACTION MECHANISM (NTWNRM-2010) , (March.17 - March

19, 2010) Department of Physics, Panjab

University, Chandigarh

6

In 2009, Director, BARC proposed the formation of a strong and sustainable Indian Nuclear Data Centre. This proposal has been accepted by Chairman, AEC.

Recently, a month ago, the formation of a strong and sustainable Indian Nuclear Data Centre has been approved by the funding agency, DAE-BRNS, and funds are being provided.

The Nuclear data Physics Centre of india (VIRTUAL) will be formally announced during this year any time.

AN EXAMPLE

TO ILLUSTRATE THAT DESIGN MANUALS OF OPERATING NUCLEAR

POWER PLANTS SHOULD BE UPDATED CONTINUALLY BASED

UPON UPDATES IN BASIC NUCLEAR DATA

BETTER NUCLEAR DATA For safe operation of existing reactors:

A practical example:

An incident involving power rise took place in KAPS, Unit 1. Nat- UO2, D2O, PHWR 220 MWe unit. A public release dated April 22, 2004 by the Atomic Energy Regulatory Board provides the details of this incident.

On March 10, 2004, KAPS-1 experienced an incident involving incapacitation of reactor regulating system, leading to an unintended rise in reactor powerfrom 73%FP to near 100%FP, with trip occurring on Steam Generator DELTA T High Level 2 on INES Scale.

February 05, 2010. 10:00 A.M.

NRFCC, BRNS, DAE Meeting; HRD hall, 1st floor, Central Complex, BARC,

Mumbai

KAPS-1 PSS ION CHAMBERS READING DURING POWER INCREASE

70

75

80

85

90

95

100 9:

08:00

9:09

:10 9:

10:20

9:11

:30 9:

12:40

9:13

:50 9:

15:00

9:16

:10 9:

17:20

9:18

:30 9:

19:40

9:20

:50 9:

22:00

9:23

:10 9:

24:20

9:25

:30 9:

26:40

9:27

:50 9:

29:00

9:30

:10

TIME

POW

ER (%

FP)

CH-D % FP

CH-E % FP

CH-F % FP

The slow rise overpower transient on March 10, 2004, KAPS-1 could not be explained by the Design manual.

The KAPS-1 overpower transient could be explained only with the use of new WIMSD multigroup nuclear libraries that give updated fuel temperature coefficients based upon improved basic nuclear data

The KAPS-1 overpower transient could be explained only with the use of new updated WLUP multigroup nuclear data libraries:

Reference: Baltej Singh, S. Ganesan, P. D. Krishanani, R. Srivenkatesan, A.N. Kumar, M.V. Parikh, H. P. Rammohan, Sherly Ray, M. P. Fernando and S. S. Bajaj, “Analysis of Power Rise Transient in KAPS-1 and Power Co-efficient Evaluation,” IAEA International conference on Operational Safety performance in Nuclear Installations, Vienna, 30 Nov. - 2 Dec. 2005.

12

Three-Stage Indian Nuclear Programme

U fueledPHWRs

Pu FueledFast Breeders

Nat. U

Dep. U

Pu

Th

Th

233U FueledBreeders

Pu

233U

Electricity

Electricity

Electricity

Stage 1 Stage 2 Stage 3

PHWR FBTR AHWR

Thorium in the centre stage

Power generation primarily by PHWRBuilding fissile inventory for stage 2

Expanding power programmeBuilding 233U inventory

Thorium utilization forSustainable power programme

233U

300 GWe-Year42000 GWe-Year

155000 GWe-Year

13

Stage – I PHWRs

• 17 - Operating• 3 - Under

construction• Several others

planned• Scaling to 700 MWe• Gestation period has

been reduced• POWER POTENTIAL

10,000 MWe

LWRs• 2 BWRs Operating• 2 VVERs under construction

8991 9086848479

75

6972

90

50

55

60

65

70

75

80

85

90

95

1995-96

1996-97

1997-98

1998-99

1999-00

2000-01

2001-02

2002-03

2003-04

2004-05

2005-06

Ava

ilabi

lity

Three Stage Nuclear Power Programme- Present Status

Stage - II Fast Breeder Reactors• 40 MWth FBTR -

Operating since 1985,Technology

Objectives realized.

• 500 MWe PFBR- Under

Construction , likley operation in 2011.

• Stage-II POWER POTENTIAL : 530,000 MWe

World class performance

Globally Advanced Technology Globally Unique

Stage - III Thorium Based Reactors

• 30 kWth KAMINI- Operating

• 300 MWe AHWR- Under Development

POWER POTENTIAL FOR STAGE-III IS VERY LARGE

Availability of ADS can enable early introduction of Thorium and enhance capacity growth rate.

14

• Currently under Pre-Licensing Safety Appraisal by AERB.

• International recognition as an innovative design.

Advanced Heavy Water Reactor (AHWR)

Major Design Objectives• Power output – 300 MWe with

500 m3/d of desalinated water.• Core heat removal by natural

circulation• A large fraction (65%) of power

from thorium. • Extensive deployment of

passive safety features – 3 days grace period, and no need for planning off-site emergency measures.

• Design life of 100 years.• Easily replaceable coolant

channels.

• Vertical pressure tube.• Boiling light water cooled.• Heavy water moderated.• Fuelled by 233U-Th MOX and Pu-

Th MOX.

Technology demonstration for large-scale thorium utilization

Schematic of ADS- energy balance

Sp

all

ati

on

targ

et

neu

tro

ns

Subcritical Core

Ta

rge

t

Accelerator

(LINAC or Cyclotron)

Energy extraction

Efficiency = e

GRID

Fraction f of the energy back to drive accelerator

Fra

cti

on

(1-

f)

of

the

en

erg

y

Accelerated protons

~ 10 MWt

~20 MWe

~ 1000 MWt @ keff= 0.98

~ 300 MWe @ he= 0.33

~ 280 MWe

15Uncertainties in PFNS will affect the design of ADSS.

16

Nuclear waste disposal by Transmutation

• Accumulation of spent fuel: a global issue.

• Spent fuel requires > 100,000 years to decay.

• Transuranic elements (TRUs: Np, Pu, Am & Cm) + a few long-lived fission products (FPs): decay very slowly.

• Bulk of FPs decay to safe disposal levels in 3-5 centuries.

• If TRUs transmuted into FPs by fission: bulk of FPs decay very fast.

Estimated

1430 - 1630 Hrs. 25 Jan. 2010

Van de Graaf seminar room, NPD.

Three Successful EXFOR workshops and sustainability by, for

instance, by recruitment of RAs.

International community (NRDC) highly appreciated and took note of India contributing more than 125 Indian EXFOR entries based upon Indian nuclear physics experiments since 2006.

Increased visibility to India’s work in nuclear physics data generation

Introduction of a new Experimental Nuclear Physics Database culture in India- A challenge.

India successfully contributed more than 120 EXFOR entries:• 10 new entries in 2006 Workshop (Faculty: Otto Schwerer Manual entries)• 31 new entries in 2007 Workshop (Faculty: Svetlana DUNAEVA, EXFOR editor)• 55 new entries in 2009 Workshop (Faculty: Svetlana DUNAEVA, EXFOR editor

software used)The details of new Indian EXFOR entries are, for instance, available in “Full EXFOR Compilation Statistics”, in the IAEA-NDS site: http:www-nds.iaea.org.exfor-master.x4compil.exfor_input.htm

• Thus far, since 2006, in all more than 120 new Indian EXFOR entries based upon experimental data generated in Indian nuclear physics experiments have been successfully made into the IAEA-EXFOR database. The identification for coding into EXFOR of all the suitable Indian articles published in the literature was done by the IAEA-NDS staff.

1430 - 1630 Hrs. 25 Jan. 2010

Over 70 delegates worked from 9:30 AM to up to 8PM every day. There were in use 20 desktop computers and another 20 individual laptops brought by delegates. This Theme Meeting was not in the nature of a seminar or conference. During the Theme Meeting, the delegates had a lot of specialist discussions and EXFOR coding tasks in a focused manner for placing the Indian experimental nuclear physics data into the IAEA EXFOR database.

The International Network of Nuclear Reaction Data Centres (NRDC) constitutes a worldwide cooperation of nuclear data centres under the auspices of the International Atomic Energy Agency.

The Network was established in the early sixties to coordinate the world-wide collection, compilation and dissemination of nuclear reaction data.

India was invited and admitted as a full member of NRDC in 2008.

INDIA WILL ACTIVELY PARTICIPATE IN PFNS COMPILATIONS IN EXFOR, RELEVANT FORE THIS CRP

Examples of other experiments and analysis in Progress:

BARC (B. K. Nayak et al., ) working on using Li-7+232Th to measure 234Pa(n,f) reaction data.

H. Naik et al., (neutron+ 234Pa) fission cross section in thermal spectrum

EXCITING SURROGATE TECHNIQUE

233Pa(n,f) Cross Section

Incident Energy (MeV)

0 5 10 15 20

Cro

ss

Se

cti

on

(b

arn

s)

-0.5

0.0

0.5

1.0

1.5

2.02004 Tovesson2004 PetitPresent ExperimentEmpire 2.19 (With Barrier Formula)

EXFOR ENTRY IN PROGRESS

EXFOR ENTRY NOS:33023 and D6075

ENSDF Evaluation Activities

The ENSDF evaluation activities and research work are being actively continued by Ashok Jain (IIT Rourkee), M. Gupta (Manipal), Gopal Mukherjee (VECC, Kolkata) and others.

The Indian Nuclear Data Centre under formation will factor into account the continuation of these important nuclear data physics activities.

India is a participant in the ITER programme

The nuclear data needs for fusion system applications is receiving increased focus and attention in India.

• Measurement of n, p and D induced activation cross sections in the MeV energy region.

• Calculations using TALYS and EMPIRE codes• FENDL library of the IAEA: Use and QA studies • Fusion integral benchmark analysis.• Use of EASY-2007 package by Robin Forrest et al.

Uncertainties in PFNS will affect the design of hybrid fusion-fission systems.

Fusion Neutronics Workshop (FNW-2007)Date: 19-22 November 2007

Nuclear Data Reliability Issues in FENDLS. GanesanReactor Physics Design DivisionBhabha Atomic Research Centre, Trombay, Mumbai-400085 India

[email protected]

[email protected]

BENCHMARKING OF INDIAN CRITICAL EXPERIMENTS

A NEW INITIATIVE BY BARC-IGCAR

INTEGRAL NUCLEAR DATA VALIDATION STUDIES

Indian experimental nuclear criticality benchmarks

History of previous benchmarking tasks:For details, please visit the URL: http://icsbep.inl.gov/

2005: India contributed the KAMINI experimental benchmark ( ICSBEP Reference: U233-MET-THERM-001 )

2008: India contributed the PURNIMA-II experimental benchmark ( ICSBEP Reference: U233-SOL-THERM-007 )2009: Work started on PURNIMA-I (PUO2 fast system)

2010: PURNIMA-I (First draft completed; march 31, 2010). Internal peer-review started.

The full report on KAMINI and PURNIMA-II benchmark sare available . See website of the ICSBEP: http://icsbep.inl.gov/ for details

INDIA HAS JOINED SELECT BAND OF COUNTRIES CONTRIBUTING TO THE ICSBEP.

BENCHMARKING KAMINI• The Kalpakkam Mini (KAMINI) is a

U-233 fueled, low power (30kW) research reactor designed and built by the BARC and IGCAR joint venture.

• One criticality configuration made on 29 Oct. 1996 has been evaluated and accepted as a benchmark.

• Benchmarking an operating system is healthier as people are unlikely to have retired and feedback from fabricators are available.

• Unique distinction being the only reactor operating with U-233 as fuel in the whole world now.

• Power – 30 kW; • Fuel – U-233 (20 Wt %

) and Al alloy• Total Fuel Inventory -

600 g of U-233• Reflector – BeO; • Moderator and

Coolant – Demineralised light water

• Core Cooling – By natural convection

• Control Elements – Cd plates

INTEGRAL NUCLEAR DATA VALIDATION STUDIES

Indian experimental nuclear criticality benchmarks

History of previous benchmarking tasks:For details, please visit the URL: http://icsbep.inl.gov/

2005: India contributed the KAMINI experimental benchmark ( ICSBEP Reference: U233-MET-THERM-001 )

2008: India contributed the PURNIMA-II experimental benchmark ( ICSBEP Reference: U233-SOL-THERM-007 )2009: Work started on PURNIMA-I (PUO2 fast system)

2010: PURNIMA-I (In Progress)


The 232U issue in thorium systems;

Role of high energy tail of the reactor spectra above the (n,2n) threshold. Here PFNS influences considerably as the initial fission neutron source.

The high energy part is very small (total flux* 10-4) and is very sensitive to reactor lattice modeling approximations. So care has to be taken to have the transport calculation be rigorous. Use Monte Carlo for instance.

Applicable to all high energy (> 4 MeV threshold ) activation cross sections

Example of EXFOR data retrieval from the Indian Mirror nuclear data website: The Figure above shows the cross section data for the nuclear reaction 232Th (n, 2n) 231Th.

Next slide shows the same data with inclusion of data from evaluations

BARC has initiated experimental campaigns to measure the data for 232Th (n, 2n) 231Th reaction in 6 to 10 MeV energy region.

The Figure above shows the cross section data for the nuclear reaction 232Th (n, 2n) 231Th with inclusion of data from evaluations.

This nuclear data is crucial in predicting 232U production in thorium fuel. The high energy tail of the reactor spectra above the (n,2n) threshold should be known accurately.. Here PFNS (topic of this CRP) influences considerably the production rate of 232U as the initial fission neutron source.

THORIUM FUEL CYCLE NUCLEAR DATA

IAEA Nuclear Data Section CRP on “Evaluated nuclear data for thorium-uranium fuel cycle”.

Data adopted in ENDF/B-VII.0

DURATION: 2002-2006

PARTICIPANTS: R. Capote (IAEA), M. Chadwick (USA), S. Ganesan (India), F.J. Hambsch (EU), O. Iwamoto (Japan), A. Ignatyuk (Russia), N. Janeva (Bulgaria), T. Kawano(USA), L. Leal (USA), Y.D. Lee (Korea), H. Leeb (Austria), P. Liu (China), V. Maslov (Belorussia), A. Plompen (EU), P. Schillebeeckx (EU), M. Sin (Romania) and A. Trkov (IAEA).

http://www-nds.iaea.org/Th-U/

THORIUM LOADING IN PHWRs

INDIA IS THE ONLY COUNTRY HAVING AN ON-GOING PROGRAMME OF THORIUM IRRADIATIONS IN ALL PHWRs FOR INITIAL POWER FLATTENING

• Thorium bundles were loaded in Indian PHWRs for initial flux flattening from KAPS Unit 1

onwards.

• Identical loading of thorium bundles also used in KAPP-2, KAIGA-1 and 2 and RAPS-3 and 4 to

attain flux flattening in the initial core.

Thorium Fuel bundle is used for power flattening in 220MWe PHWR in India

Thorium loading in the initial core of KAPS-2 unit

INDIA IS THE ONLY COUNTRY HAVING AN ON-GOING PROGRAMME OF THORIUM IRRADIATIONS IN ALL PHWRs FOR INITIAL POWER FLATTENING

Thorium loading in the initial core of KAPS-2 unit

The axial positions of the 35 bundles of thorium oxide bundles are indicated by Arabic numerals. The remaining (3025 in the active core +612 outside active core ) bundles are of natural uranium.

The Department of Physics, University of Rajathan, Jaipur

The formation of 232U in thorium

• mainly takes place by the following reactions:

232Th (n, 2n) 231Th (-) 231Pa(n, ) 232Pa (- ) 232U

• 232U is also formed in-situ with burn-up and thus 232U is also formed in small amounts through the breeding reaction from 232Th:

232Th (n, ) 233Th (-) 233Pa (- ) 233U(n, 2n) 232U.233Pa (n, 2n) 232Pa (- ) 232U

S. Ganesan3-January-2009

The Department of Physics, University of Rajathan, Jaipur

SUMMARY OF EXPERIMENTAL RESULTS: EXPERIMENTAL BENCHMARK IN PROGRESS

• J-11 (9) ThO2 bundle• 508 FPDs irradiation time ; 4.5 years cooling time

– PIED made available about 5 gms from above bundle– Dissolution studies (PDD, NRG)– Gamma spectrometric analysis (RCD )– Burnup determination - TIMS ( FCD)

Burnup 232U/233UCalculated 10,500 MWd/t ~ 100 ppm ( old) (RPDD)

540 ppm (new (RPDD)Measured 569 ppm ( FRD)

12,500 MWd/t (FCD) 549 ppm (FCD)10,800 MWd/t (RCD)

Future work • PIE of KAPS-2 Thoria bundles ; J-rods of CIRUS• FBTR thoria subassemblies - measurements of 232U & 233U

Core calculations Based Comparison of the Isotopic Contents in (J-11-9) Fuel Rod – 3rd Ring; KAPP-2 (PHWR) [Ref: V. Jagannathan, S. Ganesan and R. Srivenkatesan, “A Study on the Factors Influencing the Theoretical Estimation of 232U and Other UIsotopic Contents in Thoria Bundles Irradiated in PHWRs,” Paper submitted to INSAC-2003, 14TH ANNUAL CONFERENCE OF INDIAN NUCLEAR SOCIETY & 1ST BRNS CONFERENCE ON NUCLEAR FUEL CYCLE,December 17-19, 2003, Indira Gandhi Centre for Atomic Research Kalpakkam

C/E values for weight percent.232U 0.85233U* 1.00232U/233U(ppm) 0.86234U 0.96235U 0.92236U 0.86Sum (232U, 233U, 234U, 235U and 236U) 0.98

INDIAN CODES ARE USED: PHANTOM-CEMESH code system. Explicit treatment of (n, 2n) cross sections at Lattice LEVELLattice cell code module in PHANTOM: CLUB; *233Pa has been added.

THORIUM IN FBTR

The reasons for the expected low ppm (less than 10ppm) of 232U in Fast Breeder Test Reactor:

Nuclear data and physics considerations

• Nickel reflector brings the neutrons below the threshold of (n, 2n) reaction in 232Th;

• The effective 231Pa (n, γ) cross section is much lower in a fast spectrum as the capture cross section falls rapidly with increasing energy.

• Thirdly, the accumulation potential of 233U produced is more in saturation in a fast spectrum making the ppm content of 232U in 233U much smaller

• FACTOR OF 250 lower!!! Yet to be verified by PIE

• Proposal to measure 231Pa (n, γ) cross section in Pelletron, TIFR at 0.5MeV.

A Multi-purpose Critical Facility (CF)

Several experiments involving thorium are in progress

Critical Facility for AHWR and 500 MWe PHWR

· Validation of theoretical simulation models and Nuclear Data· The physics and engineering design completed – PSAR being

reviewed by Design Safety Review Committee

· Calandria : 330 cm dia, 500 cm height Variable pitch 20-30 cm

Nominal Reactor Fission Power: 100 WattsThermal Neutron Flux (Average): 108 n/cm2/sec72 cm bottom graphite zone 6 shut off rodsPartial Moderator Dump

Three Types of Cores:

· Reference Lattice Core : 19 rod cluster NU metal (RLC) (Dhruva pin size)

61 lattice locations (6 for SRs)27 cm pitch

· AHWR : Central 9 positions for AHWR cluster; rest RLC

· PHWR 500 : 69 lattice locations (6 for SRs) Six 37 rod standard fuel bundles per channel

Critical facility for AHWR

CRITICAL FACILITY FOR AHWR AND 500 MW(e) PHWR (Currently in Operation)

We now deal with specific discussions related to this

CRP on PFNS

BACKGROUND INFORMATION

BARC has an established expertise for study of neutron emission in fission of actinides.

Presently BARC is in the final stages of setting up a new experimental facility involving advanced neutron detectors and fission fragment detectors for carrying out high resolution prompt neutron spectra (PNS) measurements (NE213, RPC).

BARC has accelerator facilities (e.g., Pelletron and FOTIA) and research reactors based (e.g., DHURUVA) neutron source facilities.

In fact, BARC has a long tradition of interest and research programme in fission physics.

For example, the team lead by S.S. Kapoor, D. M. Nadkarni, Raja Ramanna, P. N. Rama Rao, in the early sixties had performed several interesting and new studies in neutron induced fission of U-235.


THE EXPERIMENTAL DATA NOT YET ENTERED INTO THE IAEA-EXFOR DATABASE. We will now attempt to do this important task.



THE EXPERIMENTAL DATA : NOT YET ENTERED INTO THE IAEAEXFOR DATABASE. We will now attempt to do this important task.

S. Ganesan, "Nuclear Data for Neutron Emission in the Fission Process, Proceedings of a Consultants Meeting," INDC(NDS)-251, 1991; IAEA Nuclear Data Section, 252 pages. Document avalable at http://www-nds.iaea.or.at/reports-new/indc-reports/indc-nds/indc-nds-0251.pdf

http://www-nds.iaea.or.at/reports-new/indc-reports/indc-nds/indc-nds-0251.pdf



M.S. Samant, R.P. Anand, R.K. Choudhury, S.S. Kapoor, K. Kumar, D.M. Nadkarni and A. Saxena,

“Determination of nuclear level densities of neutron rich fragment nuclei from measurement of prompt neutron emission spectra,” pp.94-103 (1991) in S. Ganesan, "Nuclear Data for Neutron Emission in the Fission Process, Proceedings of a Consultants Meeting," INDC(NDS)-251, 1991; IAEA Nuclear Data Section, 252 pages. Document available at http://www-nds.iaea.or.at/reports-new/indc-reports/indc-nds/indc-nds-0251.pdf




MEASUREMENT OF MASS DISTRIBUTION IN FISSION OF ACTINIDES232U AS AN EXAMPLE

BY RADIO CHEMISTRY DIVISION, BARC

• MEASUREMENT OF MASS DISTRIBUTION IN FISSION OF ACTINIDES • EXFOR ENTRY HAS BEEN COMPLETED• 232U AS AN EXAMPLE • BY RADIO CHEMISTRY DIVISION, BARC


The proposed research work is as follows:

1.Conduct detailed survey of available experimental and evaluated data of PNS.

2.Survey and digest available theoretical studies on PNS

3.Perform experiments with thermal as well as with a few MeV neutrons for selected actinide targets including Th-232, U-238, U-235 and U-233.

4.Perform sensitivity studies using available integral critical assembly and dosimetry data.



Presently BARC is in final stages of setting up a new and advanced experimental facility. This facility includes advanced neutron detectors and fission fragment detectors for carrying out high resolution neutron spectrum measurements using NE213 type detectors and Resistive Plate Chamber (RPC) detectors. We have expertise indigenous electronics modules and time-of-flight methodology.

BARC has accelerator facilities (e.g., Pelletron and FOTIA). We thus have accelerator facilities providing Li (p,n) based neutron source. We also have thermal and fast research reactors for neutron irradiation. Research reactors based (e.g., DHURUVA) neutron source facilities are in use for several applications.

We have some actinide targets 232Th, 238U, 235U, 233U and some MA targets but we would also like to explore the possibility of procuring some more actinide targets through the CRP mechanism, if possible.



1. Perform experimental measurement of prompt fission neutron spectra from thermal to a few MeV (4 to 5 MeV) energy range for selected actinide targets.

2. Conduct, in parallel, detailed survey of available experimental and evaluated nuclear data for prompt fission neutron spectra

3. Setup of the experimental facility for carrying out TOF studies of neutron spectra and angular correlations with respect to fission fragments. Calibration and validation of experiments with appropriate standards (252Cf) will be carried out.

4. Perform reactor sensitivity studies with different prompt fission neutron spectra to assess the impact of spectra and their uncertainties (covariances) on reactor characteristics.

5. The programme of work may be further detailed by exchange of letters between the IAEA and BARC


Expected Outputs: First Year

1. Measurements of PNS with Th-232 and U-238 targets up to 1, 2, 3 MeV using Li(p,n) neutron source. Qualification and calibration of our measurements

2. Additional targets will be procured through the IAEA grant and through the IAEA, if possible.

3. Reactor sensitivity studies with different PNS and understanding the covariance matrix generation for PNS

THANK YOU

By R.K. Choudhury (CSI), S. Ganesan, A. Saxena, B.K. Nayak, R.G. Thomas, Devesh Raj, Anek Kumar and...

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