Experimental and theoretical investigations on prompt neutron spectra and
their angular distributions for selected major and minor actinides
“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.
“Prompt fission neutron spectra of actinide nuclei”, IAEA-NDS
Experimental and theoretical investigations on prompt
neutron spectra and their angular distributions for
selected major and minor actinides
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
1st RCM Prompt Fission Neutron Spectra of
Actinides, 6-9 April 2010, IAEA, Vienna
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
The online nuclear data
services (http://wwwnds.indcentre.org.in/)
mirror the nuclear data
website of the Nuclear
Data Section of the
International Atomic
Energy Agency (IAEA),
Vienna (http://wwwnds.iaea.org).
The MOU between
DAE/BARC and the IAEA
is expected to be
continued beyond 2010.
IAEA NDS MIRROR SITE SETUP
Daily
2Mbps Link
Updates
INTERNET
NDS Mirror
Site in INDIA
IAEA Main Server
in Vienna
www-nds.iaea.org
www-nds.indcentre.org.in
Public Client
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.
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, DAEBRNS, and funds are being provided.
The Nuclear data Physics Centre of india
(VIRTUAL) will be formally announced during
this year any time.
19 March 2010
NATIONAL THEME WORKSHOP ON
NUCLEAR REACTION MECHANISM
(NTWNRM-2010) , (March.17 - March
19, 2010)
6
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.
KAPS-1 PSS ION CHAMBERS READING DURING POWER INCREASE
95
90
CH-D % FP
85
CH-E % FP
80
CH-F % FP
75
February 05, 2010. 10:00
A.M.
TIME
NRFCC, BRNS, DAE Meeting; HRD
hall, 1st floor, Central Complex, BARC,
Mumbai
9:30:10
9:29:00
9:27:50
9:26:40
9:25:30
9:24:20
9:23:10
9:22:00
9:20:50
9:19:40
9:18:30
9:17:20
9:16:10
9:15:00
9:13:50
9:12:40
9:11:30
9:10:20
9:09:10
70
9:08:00
POWER (% FP)
100
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 Coefficient Evaluation,” IAEA International conference on Operational Safety
performance in Nuclear Installations, Vienna, 30 Nov. - 2 Dec. 2005.
Three-Stage Indian Nuclear Programme
Thorium in the centre stage
PHWR
FBTR
300 GWe-Year
Nat. U
U fueled
PHWRs
AHWR
Th
42000
GWe-Year
Electricity
Dep. U
Pu Fueled
Th
Electricity
155000
GWe-Year
Fast Breeders
Pu
233U
233U
Fueled
Electricity
Breeders
Pu
Power generation primarily by PHWR
Building fissile inventory for stage 2
Stage 1
233U
Expanding power programme Thorium utilization for
Sustainable power programme
Building 233U inventory
Stage 2
Stage 3
12
Three Stage Nuclear Power Programme- Present Status
95
90
84 84 86
Availability
85
79
80
75
70
65
60
90 91 90
72
69
89
Globally Advanced
Technology
Globally Unique
75
World class
performance
55
50
1995- 1996- 1997- 1998- 1999- 2000- 2001- 2002- 2003- 2004- 200596
97
98
99
00
01
02
03
04
05
06
Stage – I PHWRs
Stage - II
Fast Breeder Reactors
• 17 - Operating
• 3 - Under construction • 40 MWth FBTR • Several others planned
Operating since 1985,
• Scaling to 700 MWe
Technology Objectives
• Gestation period has
realized.
been reduced
• 500 MWe PFBR• POWER POTENTIAL 
Under Construction ,
10,000 MWe
LWRs
• 2 BWRs Operating
• 2 VVERs under
construction
likley operation in 2011.
• Stage-II POWER
POTENTIAL :  530,000
MWe
Stage - III
Thorium Based Reactors
• 30 kWth KAMINI- Operating
• 300 MWe AHWRUnder Development
POWER POTENTIAL FOR
STAGE-III IS VERY LARGE
Availability of ADS can
enable early introduction
of Thorium and enhance
capacity growth rate.13
Advanced Heavy Water Reactor (AHWR)
•
•
•
•
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
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 offsite emergency measures.
• Design life of 100 years.
• Easily replaceable coolant channels.
•
•
Currently under Pre-Licensing
Safety Appraisal by AERB.
International recognition as an
innovative design.
14
Schematic of ADS- energy balance
Accelerated protons
GRID
Subcritical Core
~ 280 MWe
(LINAC or Cyclotron)
Target
Spallation target
neutrons
Accelerator
Fraction (1-f)
of the energy
~ 10 MWt
~20 MWe
Fraction f of the
energy back to
drive accelerator
Energy extraction
~ 1000 MWt @
keff= 0.98
Efficiency = e
~ 300 MWe @
e= 0.33
Uncertainties in PFNS will affect the design of ADSS.
15
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.
16
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.
1430 - 1630 Hrs.
2010
25 Jan.
Van de Graaf seminar room, NPD.
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:wwwnds.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.
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.
1430 - 1630 Hrs.
2010
25 Jan.
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
EXCITING SURROGATE TECHNIQUE
233
2.0
2004 Tovesson
2004 Petit
Present Experiment
Empire 2.19 (With Barrier Formula)
1.5
Cross Section (barns)
Pa(n,f) Cross Section
1.0
0.5
0.0
-0.5
0
5
10
15
20
Incident Energy (MeV)
EXFOR ENTRY
IN PROGRESS
EXFOR ENTRY
NOS:33023 and
D6075
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
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 fusionfission systems.
Nuclear Data Reliability Issues in FENDL
S. Ganesan
Reactor Physics Design
Division
Bhabha Atomic
Research Centre,
Trombay, Mumbai400085 India
ganesan@barc.gov.in
ganesan555@gmail.co
m
Fusion Neutronics Workshop (FNW-2007)
Date: 19-22 November 2007
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.
INDIA HAS JOINED SELECT BAND OF COUNTRIES
CONTRIBUTING TO THE ICSBEP.
The full report on KAMINI and PURNIMA-II benchmark s
are available . See website of the ICSBEP: http://icsbep.inl.gov/ for details
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
1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010,
IAEA, Vienna
1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010,
IAEA, Vienna
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)
1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010,
IAEA, Vienna
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
2n) 231Th reaction in 6 to 10 MeV energy region.
232Th
(n,
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
http://www-nds.iaea.org/Th-U/
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).
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 ONGOING 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. Ganesan
3-January-2009
The Department of Physics, University
of Rajathan, Jaipur
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
233U*
232U/233U(ppm)
234U
235U
236U
Sum (232U, 233U, 234U, 235U and 236U)
0.85
1.00
0.86
0.96
0.92
0.86
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:
Thermal Neutron Flux (Average):
72 cm bottom graphite zone
6 shut off rods
Partial Moderator Dump
100 Watts
108 n/cm2/sec
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
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.
1st RCM Prompt Fission Neutron Spectra of
Actinides, 6-9 April 2010, IAEA, Vienna
THE EXPERIMENTAL DATA NOT YET ENTERED INTO THE IAEAEXFOR DATABASE. We will now attempt to do this important task.
1st RCM Prompt Fission Neutron Spectra of Actinides, 6-9 April 2010, IAEA, Vienna
THE EXPERIMENTAL DATA : NOT YET ENTERED INTO THE
IAEAEXFOR DATABASE. We will now attempt to do this important
task.
1st RCM Prompt Fission Neutron Spectra of
Actinides, 6-9 April 2010, IAEA, Vienna
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://wwwnds.iaea.or.at/reports-new/indcreports/indc-nds/indc-nds0251.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/indcnds/indc-nds-0251.pdf
1st RCM Prompt Fission Neutron Spectra of
Actinides, 6-9 April 2010, IAEA, Vienna
MEASUREMENT OF MASS DISTRIBUTION IN FISSION OF
ACTINIDES
232U
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 Th232, U-238, U-235 and U-233.
4.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
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.
1st RCM Prompt Fission Neutron Spectra of
Actinides, 6-9 April 2010, IAEA, Vienna
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