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 ID: 930962
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Slide1
Discussion of Research Proposal and Expected outputs Benchmark PerformanceTITLE 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
By
R.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.
Slide2A new IAEA CRP:“Prompt fission neutron spectra of actinide nuclei”, IAEA-NDSTITLE OF RESEARCH CONTRACT PROPOSAL:Experimental and theoretical investigations on prompt neutron spectra and their angular distributions for selected major and minor actinides1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, ViennaDiscussion of Research Proposal and Expected outputs
Benchmark Performance
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:
ganesan@barc.gov.in
ganesan555@gmail.com
Slide3NUCLEAR DATA ACTIVITIES IN INDIABasic 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 facilityNew 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, TALYSProcessing of evaluated nuclear data files to produce plug-in libraries for discrete ordinates and Monte Carlo codes. NJOY (USA) equivalent to be developedEfforts to digest the status of covariance error methodology in nuclear data and its applications. A beginning with a DAE-BRNS Project at ManipalPreparation 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)
Slide4Indian nuclear data mirror website at Mumbai http://www-nds.indcentre.org.in
Slide5INTERNETIAEA Main Server in ViennaPublic ClientNDS Mirror Site in INDIAIAEA 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.
Slide619 March 2010 NATIONAL THEME WORKSHOP ON NUCLEAR REACTION MECHANISM (NTWNRM-2010) , (March.17 - March 19, 2010) Department of Physics, Panjab University, Chandigarh 6In 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.
Slide7AN EXAMPLE TO ILLUSTRATE THAT DESIGN MANUALS OF OPERATING NUCLEAR POWER PLANTS SHOULD BE UPDATED CONTINUALLY BASED UPON UPDATES IN BASIC NUCLEAR DATA
Slide8BETTER 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.
Slide9February 05, 2010. 10:00 A.M.NRFCC, BRNS, DAE Meeting; HRD hall, 1st floor, Central Complex, BARC, Mumbai
Slide10The 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
Slide11The 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.
Slide1212Three-Stage Indian Nuclear Programme
U fueled
PHWRs
Pu Fueled
Fast Breeders
Nat. U
Dep. U
Pu
Th
Th
233
U Fueled
Breeders
Pu
233
U
Electricity
Electricity
Electricity
Stage 1
Stage 2
Stage 3
PHWR
FBTR
AHWR
Thorium in the centre stage
Power generation primarily by PHWR
Building fissile inventory for stage 2
Expanding power programme
Building
233
U
inventory
Thorium utilization for
Sustainable power programme
233
U
300 GWe-Year
42000 GWe-Year
155000
GWe-Year
Slide1313Stage – 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
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.
Slide1414Currently under Pre-Licensing Safety Appraisal by AERB.International recognition as an innovative design.Advanced Heavy Water Reactor (AHWR)Major Design ObjectivesPower output – 300 MWe with 500 m3/d of desalinated water.Core heat removal by natural circulationA 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
233
U-Th MOX and Pu-Th MOX.
Technology demonstration for large-scale thorium utilization
Slide15Schematic of ADS- energy balance~ 10 MWt~20 MWe~ 1000 MWt @ keff= 0.98~ 300 MWe @ he= 0.33~ 280 MWe15Uncertainties in PFNS will affect the design of ADSS.
Slide1616Nuclear waste disposal by TransmutationAccumulation 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
Slide171430 - 1630 Hrs. 25 Jan. 2010Van 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.
Slide18India 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.
Slide191430 - 1630 Hrs. 25 Jan. 2010Over 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.
Slide20The 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
Slide21Slide22Examples 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 spectrumEXCITING SURROGATE TECHNIQUEEXFOR ENTRY IN PROGRESSEXFOR ENTRY NOS:33023 and D6075
Slide23ENSDF Evaluation ActivitiesThe 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.
Slide24India is a participant in the ITER programmeThe 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 codesFENDL 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.
Slide25Fusion Neutronics Workshop (FNW-2007)Date: 19-22 November 2007Nuclear Data Reliability Issues in FENDLS. GanesanReactor Physics Design DivisionBhabha Atomic Research Centre, Trombay, Mumbai-400085 Indiaganesan@barc.gov.inganesan555@gmail.com
Slide26BENCHMARKING OF INDIAN CRITICAL EXPERIMENTSA NEW INITIATIVE BY BARC-IGCAR
Slide27INTEGRAL 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.
Slide28The full report on KAMINI and PURNIMA-II benchmark sare available . See website of the ICSBEP: http://icsbep.inl.gov/ for detailsINDIA HAS JOINED SELECT BAND OF COUNTRIES CONTRIBUTING TO THE ICSBEP.
Slide29BENCHMARKING KAMINIThe 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.
Slide30Power – 30 kW; Fuel – U-233 (20 Wt % ) and Al alloyTotal Fuel Inventory - 600 g of U-233Reflector – BeO; Moderator and Coolant – Demineralised light waterCore Cooling – By natural convectionControl Elements – Cd plates
Slide311st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna
Slide321st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna
Slide33INTEGRAL 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)
1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna
Slide34The 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
Slide35Example 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 evaluationsBARC has initiated experimental campaigns to measure the data for 232Th (n, 2n) 231Th reaction in 6 to 10 MeV energy region.
Slide36The 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.
Slide37THORIUM FUEL CYCLE NUCLEAR DATAIAEA Nuclear Data Section CRP on “Evaluated nuclear data for thorium-uranium fuel cycle”.Data adopted in ENDF/B-VII.0DURATION: 2002-2006PARTICIPANTS: 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/
Slide38THORIUM LOADING IN PHWRsINDIA IS THE ONLY COUNTRY HAVING AN ON-GOING PROGRAMME OF THORIUM IRRADIATIONS IN ALL PHWRs FOR INITIAL POWER FLATTENING
Slide39Thorium 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.
Slide40Thorium Fuel bundle is used for power flattening in 220MWe PHWR in India
Slide41Thorium loading in the initial core of KAPS-2 unitINDIA IS THE ONLY COUNTRY HAVING AN ON-GOING PROGRAMME OF THORIUM IRRADIATIONS IN ALL PHWRs FOR INITIAL POWER FLATTENINGThorium loading in the initial core of KAPS-2 unitThe 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.
Slide42The Department of Physics, University of Rajathan, Jaipur
Slide43Slide44The formation of 232U in thoriummainly takes place by the following reactions:232Th (n, 2n) 231Th (-) 231Pa(n, ) 232Pa (- ) 232U232U 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 (
-)
233
Pa (
- )
233
U(n, 2n)
232
U.
233
Pa (n, 2n)
232
Pa (
- )
232
U
Slide45S. Ganesan3-January-2009 The Department of Physics, University of Rajathan, Jaipur
Slide46Core 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/
233
U(
ppm
) 0.86
234
U 0.96
235
U 0.92
236
U 0.86
Sum (
232
U,
233
U,
234
U,
235
U and
236
U)
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;
*
233
Pa has been added.
Slide47THORIUM IN FBTR
Slide48Slide49The 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 smallerFACTOR OF 250 lower!!! Yet to be verified by PIEProposal to measure 231Pa (n, γ) cross section in Pelletron, TIFR at 0.5MeV.
Slide50A Multi-purpose Critical Facility (CF)Several experiments involving thorium are in progress
Slide51Critical 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 CommitteeCalandria : 330 cm dia, 500 cm height Variable pitch 20-30 cmNominal 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 pitchAHWR : Central 9 positions for AHWR cluster; rest RLC
PHWR 500 : 69 lattice locations (6 for SRs)
Six 37 rod standard fuel bundles per channel
Slide52Critical facility for AHWR
Slide53CRITICAL FACILITY FOR AHWR AND 500 MW(e) PHWR (Currently in Operation)
Slide54We now deal with specific discussions related to this CRP on PFNS
Slide55BACKGROUND INFORMATIONBARC 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.
1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna
Slide56THE EXPERIMENTAL DATA NOT YET ENTERED INTO THE IAEA-EXFOR DATABASE. We will now attempt to do this important task.1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna
Slide571st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, ViennaTHE EXPERIMENTAL DATA : NOT YET ENTERED INTO THE IAEAEXFOR DATABASE. We will now attempt to do this important task.
Slide58Slide59S. 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
Slide60M.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.pdf1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna
Slide61MEASUREMENT OF MASS DISTRIBUTION IN FISSION OF ACTINIDES232U AS AN EXAMPLE BY RADIO CHEMISTRY DIVISION, BARC
Slide62MEASUREMENT OF MASS DISTRIBUTION IN FISSION OF ACTINIDES EXFOR ENTRY HAS BEEN COMPLETED232U AS AN EXAMPLE BY RADIO CHEMISTRY DIVISION, BARC
Slide63Discussion of Research Proposal and Expected outputs Benchmark Performance The proposed research work is as follows:Conduct detailed survey of available experimental and evaluated data of PNS.Survey and digest available theoretical studies on PNSPerform 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.Perform sensitivity studies using available integral critical assembly and
dosimetry
data.
1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna
Slide64Discussion of Research Proposal and Expected outputs Benchmark Performance 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
232
Th,
238
U,
235
U,
233
U 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.
1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna
Slide65Discussion of Research Proposal and Expected outputs Benchmark Performance Perform experimental measurement of prompt fission neutron spectra from thermal to a few MeV (4 to 5 MeV) energy range for selected actinide targets.Conduct, in parallel, detailed survey of available experimental and evaluated nuclear data for prompt fission neutron spectra 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.Perform reactor sensitivity studies with different prompt fission neutron spectra to assess the impact of spectra and their uncertainties (covariances) on reactor characteristics.
The programme of work may be further detailed by exchange of letters between the IAEA and BARC
Slide66Discussion of Research Proposal and Expected outputs Benchmark Performance Expected Outputs: First Year 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 measurementsAdditional targets will be procured through the IAEA grant and through the IAEA, if possible.Reactor sensitivity studies with different PNS and understanding the covariance matrix generation for PNS
Slide67THANK YOU