Challenges in nuclear data evaluation of actinide nuclei

Size: px
Start display at page:

Download "Challenges in nuclear data evaluation of actinide nuclei"

Transcription

1 Challenges in nuclear data evaluation of actinide nuclei 1 Roberto Capote NAPC - Nuclear Data Section, IAEA, Vienna, Austria

2 Thanks to: Organizers for the invitation/support All collaborators o A. Trkov (IAEA) o M. Sin (Univ. Bucharest) o D. Bernard and G. Noguere (CEA) o Y. Danon and A. Daskalakis (RPI) o M.W. Herman (BNL) o B.V.Carlson (ITA) 2

3 OUTLOOK Introduction and motivation Experimental challenges (from an evaluator point of view) Modelling challenges Evaluation methodology challenges Challenges in use of integral data 3

4 Why we need ADS/fast reactors? FERTILE ( 235 U, 233 U ) FISSILE 4

5 Neutron induced reactions on U-238 (n,el) (n,tot) (n,g) (n,inel) (n,f) (n,2n) 5

6 Experimental challenges (biased) 1. Quasi-differential experiments (~RPI) for 235 U, 239 Pu, 232 Th, 237 Np Goal: better elastic an inelastic scattering from 0.5 to 10 MeV 2. SPA cross sections measurements in 235 U and 239 Pu PFNS fields ( inelastic and n,2n reactions) Goal: better PFNS below 700 kev and above 8 MeV, PFNS validation 6

7 RPI quasidifferential data measured on Zr (published) and 238 U 7

8 8

9 RPI experimental setup 9

10 RPI benchmark:

11 Angle dependent cross sections (n,f) (n,n ) cont (n,2n) 11

12 SPA cross sections measurements in 235 U and 239 Pu PFNS thermal fields 12

13 C/E Cf(sf) PFNS Average: / E50%-response [MeV] 13

14 C/E ENDF/B-VII U(n th,f) PFNS Average: / (E50% < 11 MeV) E50%-response in [MeV] 14

15 (Nuclear reaction) modelling challenges 15

16 total (and 1 st lev ) inelastic cross sections 16

17 cross sections [mb] new physics: DIR-CN interference Engelbrecht-Weidenmuller transformation [1] (n,el) dir-cn interference elastic 1 st level (44.9) 2 nd level (148) no interference elastic 1 st level (44.9) 2 nd level (148) 1000 (n,n 1 ) energy [MeV] [1] C.A. Engelbrecht, H.A. Weidenmuller, Hauser--Feshbach theory and Ericson fluctuations in the presence of direct reactions, Phys.Rev. C8 (1974)

18 MODELLING CHALLENGES 238 U(n,n g) (gsb) kev 5/ /2 (gs) 235 U(n,n g) Bacquias/Kerveno et al (prelim., unpublished) Kerveno et al, PRC87(2013) Better structure models => CC OMP 18

19 Rigid rotor with soft-rotor corrections U-238 Yu.V.Porodzinkij and E. Soukhovitdkii, Phys. At. Nuclei 59 (1996)

20 Evaluation methodology challenges 20

21 Evaluation Methodology Challenges Use nuclear reaction modelling code (e.g EMPIRE) Choose adequate model options (HF+fluct., direct, PE) Determine needed input parameters (starting from RIPL) Calculate cross sections and other quantities Compare calculated values to selected measured data (after correcting for new stds, discarding discrepant, etc) Fine-tune the input model parameters Loop-1 From model parameter uncertainties and model uncertainties generate covariance matrix prior Do the GLSQ fit to combine the EXP and model data 21

22 Evaluation Methodology Challenges 1) MC modeling (EMPIRE, TALYS, CCONE, CoH, ) {σ i } exp 2) For each random set {σ i } we calculate L(y E,V E σ i ) L(y E,V E σ i ) = exp{-(½)[(f (σ i ) y E ) T ( V E ) -1 (f (σ i ) y E )]} N i 1 w N i 1 exp w ( ) exp OUTPUT: 1) i ( ) i, i, w ( i) cov(, i Unified Monte Carlo cov(, i j UMC-B ) j ) i j i j 22 2) Stochastic set {σ i } (e.g. to be used in TMC)

23 Evaluation Methodology Challenges ALTERNATIVES to GLSQ: MC methods: No covariance generation UMC-B : Solution is obtained as a linear combination of model results However: The solution may not be reproducible by model calculations (more information is derived from experimental data => overcome model defects) 23

24 Challenges in use of integral data JEZEBEL Compensating errors!! LANL, USA INDC(NDS)-0597 A.J. Plompen et al 24

25 Challenges in use of integral data Compensating errors: Elastic vs Inelastic Cross-correlations among isotopes: e.g. Flattop-25 critical assembly 235 U (PFNS) and 238 U (elastic and inelastic) RELATED 25

26 elastic -bar (P1 component) 26

27 Elastic angular distribution 720 kev impact on reflectors beyond -bar (P1)! 27

28 CONCLUSIONS Experimental challenges New quasi-diff. and SPA cross-section meas. Modelling challenges Better structure in reaction calcs (CC OMPs) Evaluation methodology challenges Going beyond model calcs (e.g. UMC-B) Challenges in use of integral data Cross-isotope correlations 28

EVALUATION OF NEUTRON INDUCED REACTIONS ON 238 U NUCLEUS

EVALUATION OF NEUTRON INDUCED REACTIONS ON 238 U NUCLEUS EVALUATION OF NEUTRON INDUCED REACTIONS ON 238 U NUCLEUS UN complex 1/27 Roberto Capote, NAPC - Nuclear Data Section, IAEA, Austria Andrej Trkov, Jozef Stefan Institute, Slovenia Mihaela Sin, University

More information

(NUCLEAR) DATA EVALUATION METHODOLOGY INCLUDING ESTIMATES OF COVARIANCE

(NUCLEAR) DATA EVALUATION METHODOLOGY INCLUDING ESTIMATES OF COVARIANCE (NUCLEAR) DATA EVALUATION METHODOLOGY INCLUDING ESTIMATES OF COVARIANCE Roberto Capote International Atomic Energy Agency NAPC - Nuclear Data Section Thanks to my collaborators Andrej Trkov Josef Stefan

More information

Unified Monte Carlo evaluation method

Unified Monte Carlo evaluation method Unified Monte Carlo evaluation method IAEA Roberto Capote and Andrej Trkov IAEA Nuclear Data Section, Vienna, Austria Donald L. Smith, Argonne National Laboratory, USA (Nuclear) Data Evaluation & correl

More information

Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May 2010

Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May 2010 2141-34 Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies 3-14 May 2010 Monte Carlo Approaches for Model Evaluation of Cross Sections and Uncertainties CAPOTE R. IAEA

More information

Statistical Model Calculations for Neutron Radiative Capture Process

Statistical Model Calculations for Neutron Radiative Capture Process Statistical Nuclear Physics and its Applications in Astrophysics, Jul. 8-, 2008 Statistical Model Calculations for Neutron Radiative Capture Process T. Kawano T-6 Nuclear Physics Los Alamos National Laboratory

More information

Physics of Neutron Interactions with 238 U: New Developments and Challenges

Physics of Neutron Interactions with 238 U: New Developments and Challenges Available online at www.sciencedirect.com Nuclear Data Sheets 118 (2014) 26 31 www.elsevier.com/locate/nds Physics of Neutron Interactions with 238 U: New Developments and Challenges R. Capote, 1, A. Trkov,

More information

Needs for Nuclear Reactions on Actinides

Needs for Nuclear Reactions on Actinides Needs for Nuclear Reactions on Actinides Mark Chadwick Los Alamos National Laboratory Talk at the Workshop on Nuclear Data Needs & Capabilities for Applications, May 27-29, 2015 Nuclear Data for National

More information

Physics of Neutron Interactions with 238 U: New Developments and Challenges

Physics of Neutron Interactions with 238 U: New Developments and Challenges Physics of Neutron Interactions with 38 U: New Developments and Challenges R. Capote,, A. Trkov, M. Sin, 3 M. Herman, 4 A. Daskalakis, 5 and Y. Danon 5 NAPC Nuclear Data Section, International Atomic Energy

More information

Status of Subgroup 24

Status of Subgroup 24 Status of Subgroup 24 M. Herman National Nuclear Data Center, BNL for SG24 mwherman@bnl.gov Brookhaven Science Associates SG 24 membership M. Herman (BNL) - Chairman C. Mattoon (BNL) S. Mughaghab (BNL)

More information

Preliminary Uncertainty Analysis at ANL

Preliminary Uncertainty Analysis at ANL Preliminary Uncertainty Analysis at ANL OECD/NEA WPEC Subgroup 33 Meeting November 30, 2010 Paris, France W. S. Yang, G. Aliberti, R. D. McKnight Nuclear Engineering Division Argonne National Laboratory

More information

CIELO Project. M. Herman 1) D. Brown 1), R. Capote 2), G. Nobre 1), A. Trkov 2) for the CIELO Collaboration 3)

CIELO Project. M. Herman 1) D. Brown 1), R. Capote 2), G. Nobre 1), A. Trkov 2) for the CIELO Collaboration 3) 56Fe Evaluation for the CIELO Project M. Herman 1) D. Brown 1), R. Capote 2), G. Nobre 1), A. Trkov 2) for the CIELO Collaboration 3) 1) National Nuclear Data Center, Brookhaven National Laboratory, USA

More information

Nuclear Data Evaluation of 55 Mn by the EMPIRE code with Emphasis on the Capture Cross Section

Nuclear Data Evaluation of 55 Mn by the EMPIRE code with Emphasis on the Capture Cross Section International Conference Nuccllearr Enerrgy fforr New Eurrope 2009 Bled / Slovenia / September 14-17 ABSTRACT Nuclear Data Evaluation of 55 Mn by the EMPIRE code with Emphasis on the Capture Cross Section

More information

Available online at ScienceDirect. Physics Procedia 64 (2015 ) 48 54

Available online at   ScienceDirect. Physics Procedia 64 (2015 ) 48 54 Available online at www.sciencedirect.com ScienceDirect Physics Procedia 64 (2015 ) 48 54 Scientific Workshop on Nuclear Fission dynamics and the Emission of Prompt Neutrons and Gamma Rays, THEORY-3 Evaluation

More information

SG39 Meeting May 16-17, Update on Continuous Energy Cross Section Adjustment. UC Berkeley / INL collaboration

SG39 Meeting May 16-17, Update on Continuous Energy Cross Section Adjustment. UC Berkeley / INL collaboration SG39 Meeting May 16-17, 2017 Update on Continuous Energy Cross Section Adjustment. UC Berkeley / INL collaboration Outline Presentation of the proposed methodology (you've already seen this) Results from

More information

Neutron-induced reactions on U and Th a new approach via AMS in collaboration with: KIT (Karlsruhe): F. Käppeler, I. Dillmann

Neutron-induced reactions on U and Th a new approach via AMS in collaboration with: KIT (Karlsruhe): F. Käppeler, I. Dillmann Neutron-induced reactions on U and Th a new approach via AMS in collaboration with: KIT (Karlsruhe): F. Käppeler, I. Dillmann IRMM / Geel: A. Plompen, A. Krasa IKI Budapest: T. Belgya, L. Szentmiklosi

More information

Calculation of uncertainties on DD, DT n/γ flux at potential irradiation positions (vertical ports) and KN2 U3 by TMC code (L11) Henrik Sjöstrand

Calculation of uncertainties on DD, DT n/γ flux at potential irradiation positions (vertical ports) and KN2 U3 by TMC code (L11) Henrik Sjöstrand Calculation of uncertainties on DD, DT n/γ flux at potential irradiation positions (vertical ports) and KN2 U3 by TMC code (L11) Henrik Sjöstrand Acknowledgements Henrik Sjöstrand and JET Contributors*

More information

B. Morillon, L. Leal?, G. Noguere y, P. Romain, H. Duarte. April U, 238 U and 239 Pu JEFF-3.3T1 evaluations

B. Morillon, L. Leal?, G. Noguere y, P. Romain, H. Duarte. April U, 238 U and 239 Pu JEFF-3.3T1 evaluations B. Morillon, L. Leal?, G. Noguere y, P. Romain, H. Duarte CEA,DAM,DIF F-9297 Arpajon, France y CEA,DEN Cadarache, France? IRSN 92260 Fontenay-aux-Roses, France April 206 239 Pu : what's new New FILES 2,

More information

Latest experimental results on (n,xnγ) on 235U and 238U

Latest experimental results on (n,xnγ) on 235U and 238U Latest experimental results on (n,xnγ) on 235 and 238 CNRS-IPHC Strasbourg A. Bacquias, Ph. Dessagne, G. Henning, H. Karam, M. Kerveno, G. Rudolf, J.C. Thiry JRC-IRMM Geel J.C. Drohé, N. Nankov, M. Nyman,

More information

PIA and REWIND: Two New Methodologies for Cross Section Adjustment. G. Palmiotti and M. Salvatores

PIA and REWIND: Two New Methodologies for Cross Section Adjustment. G. Palmiotti and M. Salvatores PIA and REWIND: Two New Methodologies for Cross Section Adjustment G. Palmiotti and M. Salvatores Nuclear Systems Design and Analysis Division, Idaho National Laboratory, P.O. Box 1625, MS 3860, Idaho

More information

Correlated Prompt Fission Data

Correlated Prompt Fission Data Correlated Prompt Fission Data Patrick Talou 1, T. Kawano 1, I. Stetcu 1, D. Neudecker 2 1 Theoretical Division, Los Alamos National Laboratory, USA 2 XCP-5, Computational Physics Division, Los Alamos

More information

Potential Use of beta-eff and other Benchmarks for Adjustment

Potential Use of beta-eff and other Benchmarks for Adjustment Potential Use of beta-eff and other Benchmarks for Adjustment Ivo Kodeli SG39 Meeting, NEA, May 19, 2015 Analysed benchmarks from ICSBEP and IRPhE SNEAK-7A & -7B: MOX fuel reflected by metallic depleted

More information

TENDL-TMC for dpa and pka

TENDL-TMC for dpa and pka WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN D. Rochman, A.J. Koning, J.C. Sublet, M. Gilbert, H. Sjöstrand, P. Helgesson and H. Ferroukhi TENDL-TMC for dpa and pka Technical Meeting on Uncertainties for Radiation

More information

NUCLEAR DATA VERIFICATION USING GALILEE AND TRIPOLI-4

NUCLEAR DATA VERIFICATION USING GALILEE AND TRIPOLI-4 NUCLEAR DATA VERIFICATION USING GALILEE AND TRIPOLI-4 C. Jouanne (CEA Saclay) WPEC-SG43 MAY 2018 PAGE 1 VERIFICATION GALILEE-1 Code : GALVANE Module (GALilée Verification of the Accuracy of Nuclear Evaluations)

More information

LA-UR Approved for public release; distribution is unlimited.

LA-UR Approved for public release; distribution is unlimited. LA-UR-16-24091 Approved for public release; distribution is unlimited. Title: Author(s): Going beyond generalized least squares algorithms for estimating nuclear data observables Neudecker, Denise Helgesson,

More information

Measurement of (n, xn γ) reaction cross sections in W isotopes

Measurement of (n, xn γ) reaction cross sections in W isotopes Measurement of (n, xn γ) reaction cross sections in isotopes Greg Henning IPHC/CNRS 1 Context: Nuclear data evaluations for applications 4 th generation nuclear reactors and new fuel cycles, currently

More information

Improved nuclear data for material damage applications in LWR spectra

Improved nuclear data for material damage applications in LWR spectra Improved nuclear data for material damage applications in LWR spectra Focus on uncertainties, 59 Ni, and stainless steel Petter Helgesson,2 Henrik Sjöstrand Arjan J. Koning 3, Dimitri Rochman 4 Stephan

More information

Angular and energy distributions of the prompt fission neutrons from thermal neutron-induced fission of 239 Pu

Angular and energy distributions of the prompt fission neutrons from thermal neutron-induced fission of 239 Pu Angular and energy distributions of the prompt fission neutrons from thermal neutron-induced fission of 239 Pu Vorobyev AS, Shcherbakov OA, Gagarski AM, Val ski GV, Petrov GA National Research Center Kurchatov

More information

The updated version of the Chinese Evaluated Nuclear Data Library (CENDL-3.1) and China nuclear data evaluation activities

The updated version of the Chinese Evaluated Nuclear Data Library (CENDL-3.1) and China nuclear data evaluation activities International Conference on Nuclear Data for Science and Technology 2007 DOI: 10.1051/ndata:07570 Invited The updated version of the Chinese Evaluated Nuclear Data Library (CENDL-3.1) and China nuclear

More information

Status of ENDF/B-VII.1 library

Status of ENDF/B-VII.1 library Status of ENDF/B-VII.1 library Report to WPEC, May 12-13, 2011, NEA Headquarters, Paris, France M. Herman for CSEWG National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000, USA

More information

Review of nuclear data of major actinides and 56 Fe in JENDL-4.0

Review of nuclear data of major actinides and 56 Fe in JENDL-4.0 Review of nuclear data of major actinides and 56 Fe in JENDL-4.0 Osamu Iwamoto, Nobuyuki Iwamoto Nuclear Data Center, Nuclear Science and Engineering Directorate Japan Atomic Energy Agency Ibaraki, Japan

More information

Perspective on CIELO. Michael Dunn Nuclear Data & Criticality Safety Group Leader. NEMEA-7 / CIELO Workshop Geel, Belgium November 5-8, 2013

Perspective on CIELO. Michael Dunn Nuclear Data & Criticality Safety Group Leader. NEMEA-7 / CIELO Workshop Geel, Belgium November 5-8, 2013 Perspective on CIELO Michael Dunn Nuclear Data & Criticality Safety Group Leader NEMEA-7 / CIELO Workshop Geel, Belgium November 5-8, 2013 Introductory Comments Perspective from multiple view points ORNL

More information

arxiv: v1 [nucl-th] 17 Jan 2019

arxiv: v1 [nucl-th] 17 Jan 2019 Unified Coupled-Channels and Hauser-Feshbach Model Calculation for Nuclear Data Evaluation Toshihiko Kawano Los Alamos National Laboratory, Los Alamos, NM 87545, USA Email: kawano@lanl.gov arxiv:191.5641v1

More information

Invited. The latest BROND-3 developments. 1 Introduction. 2 Cross section evaluations for actinides

Invited. The latest BROND-3 developments. 1 Introduction. 2 Cross section evaluations for actinides International Conference on Nuclear Data for Science and Technology 2007 DOI: 10.1051/ndata:07641 Invited The latest developments A.V. Ignatyuk a and B.I. Fursov Institute of Physics and Power Engineering,

More information

Elastic and inelastic scattering of neutrons on 238 U nucleus

Elastic and inelastic scattering of neutrons on 238 U nucleus EPJ Web of Conferences 69, 00008 (204) DOI: 0.05/ epjconf/2046900008 C Owned by the authors, published by EDP Sciences, 204 Elastic and inelastic scattering of neutrons on 238 U nucleus R. Capote,a,A.Trkov,2,M.Sin

More information

ENDF8. M.B. Chadwick LANL. Mark Chadwick, LANL. WPEC-SG40 (CIELO), Paris, May17, Operated by Los Alamos National Security, LLC for NNSA

ENDF8. M.B. Chadwick LANL. Mark Chadwick, LANL. WPEC-SG40 (CIELO), Paris, May17, Operated by Los Alamos National Security, LLC for NNSA ENDF8 M.B. Chadwick LANL Mark Chadwick, LANL WPEC-SG40 (CIELO), Paris, May17, 2017 International CIELO Collaboration Experiments: Some of the many experimental facilities that measured new data supporting

More information

ORNL Nuclear Data Evaluation Accomplishments for FY 2013

ORNL Nuclear Data Evaluation Accomplishments for FY 2013 ORNL Nuclear Data Evaluation Accomplishments for FY 2013 L. Leal, V. Sobes, M. Pigni, K. Guber, G. Arbanas, D. Wiarda, M. Dunn (ORNL) and E. Ivanov, T. Ivanova, E. Letang (Institut de Radioprotection et

More information

Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study

Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study M. Salvatores, 1, 2, G. Palmiotti, 2 G. Aliberti, 3 P. Archier, 1

More information

INDC International Nuclear Data Committee

INDC International Nuclear Data Committee International Atomic Energy Agency INDC(NDS)-0597 Distr. J+NM INDC International Nuclear Data Committee Summary Report Technical Meeting on Inelastic Scattering and Capture Cross-section Data of Major

More information

Invited. ENDF/B-VII data testing with ICSBEP benchmarks. 1 Introduction. 2 Discussion

Invited. ENDF/B-VII data testing with ICSBEP benchmarks. 1 Introduction. 2 Discussion International Conference on Nuclear Data for Science and Technology 2007 DOI: 10.1051/ndata:07285 Invited ENDF/B-VII data testing with ICSBEP benchmarks A.C. Kahler and R.E. MacFarlane Los Alamos National

More information

Microscopic cross sections : an utopia? S. Hilaire 1, A.J. Koning 2 & S. Goriely 3.

Microscopic cross sections : an utopia? S. Hilaire 1, A.J. Koning 2 & S. Goriely 3. Microscopic cross sections : an utopia? S. Hilaire 1, A.J. Koning 2 & S. Goriely 3 www.talys.eu 1 CEA,DAM,DIF - France 2 Nuclear Research and Consultancy Group, Petten, The Netherlands 3 Institut d Astronomie

More information

Development of Multigroup Cross Section Generation Code MC 2-3 for Fast Reactor Analysis

Development of Multigroup Cross Section Generation Code MC 2-3 for Fast Reactor Analysis Development o Multigroup Cross Section Generation Code MC 2-3 or Fast Reactor Analysis International Conerence on Fast Reactors and Related Fuel Cycles December 7-11, 2009 Kyoto, Japan Changho Lee and

More information

Statistical-Model and Direct-Semidirect-Model Calculations of Neutron Radiative Capture Process

Statistical-Model and Direct-Semidirect-Model Calculations of Neutron Radiative Capture Process New Era of Nuclear Physics in the Cosmos, the r-process Nucleo-Synthesis RIKEN, Japan, Sep. 25,26, 2008 Statistical-Model and Direct-Semidirect-Model Calculations of Neutron Radiative Capture Process T.

More information

Monte Carlo Nuclear Data Assimilation via integral information

Monte Carlo Nuclear Data Assimilation via integral information Long-term international collaboration to improve nuclear data evaluation and evaluated data files meeting, 18-21 December 2017, IAEA, Vienna, Austria D. Rochman 1, E. Bauge 2, A.J. Koning 3 and J.Ch. Sublet

More information

In collaboration with NRG

In collaboration with NRG COMPARISON OF MONTE CARLO UNCERTAINTY PROPAGATION APPROACHES IN ACTIVATION CALCULATIONS Carlos J. Díez*, O. Cabellos, J.S. Martínez Universidad Politécnica de Madrid (UPM) CCFE (UK), January 24, 2012 In

More information

Nuclear Data Section Department of Nuclear Sciences and Applications

Nuclear Data Section Department of Nuclear Sciences and Applications Advances in Nuclear Data RA Forrest Nuclear Data Section Department of Nuclear Sciences and Applications Introduction Nuclear Data underpin all of Nuclear Science and Technology Nuclear Data include static

More information

Chapter 5: Applications Fission simulations

Chapter 5: Applications Fission simulations Chapter 5: Applications Fission simulations 1 Using fission in FISPACT-II FISPACT-II is distributed with a variety of fission yields and decay data, just as incident particle cross sections, etc. Fission

More information

PIA: Progressive Incremental Adjustment

PIA: Progressive Incremental Adjustment PIA: Progressive Incremental Adjustment G. Palmiotti 1, M.Salvatores 1,2 1 Idaho National Laboratory, 2 Consultant, November 28, 2014 December 2012 SG39, Paris, France The problem of compensations In many

More information

The Updated Version of Chinese Evaluated Nuclear Data Library (CENDL-3.1)

The Updated Version of Chinese Evaluated Nuclear Data Library (CENDL-3.1) Journal of the Korean Physical Society, Vol. 59, No. 2, August 2011, pp. 1052 1056 The Updated Version of Chinese Evaluated Nuclear Data Library (CENDL-3.1) Z. G. Ge, Z. X. Zhao and H. H. Xia China Nuclear

More information

TENDL 2017: better cross sections, better covariances

TENDL 2017: better cross sections, better covariances WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN D. Rochman TENDL 2017: better cross sections, better covariances Workshop on TALYS/TENDL Developments, 13 15 November 2017, Prague, Czech Republic Summary Short history,

More information

Uncertainty quantification using SCALE 6.2 package and GPT techniques implemented in Serpent 2

Uncertainty quantification using SCALE 6.2 package and GPT techniques implemented in Serpent 2 6th International Serpent User Group Meeting Politecnico di Milano, Milan, Italy September 26 th -30 th, 2016 Uncertainty quantification using SCALE 6.2 package and GPT techniques implemented in Serpent

More information

Photonuclear Activation File. Status and Perspectives

Photonuclear Activation File. Status and Perspectives Photonuclear Activation File ((( P A F ))) Status and Perspectives M-L. Giacri, A. Vanlauwe, J-C. David, D. Doré, D. Ridikas, I. Raskinyte, E. Dupont, V. Macary CEA Saclay, DSM/Dapnia/SPhN http://www-dapnia.cea.fr/sphn/mnm/

More information

CIELO: Status of Cross Section Progress

CIELO: Status of Cross Section Progress CIELO: Status of Cross Section Progress M.B. Chadwick, A.C. Kahler, T. Kawano, P. Talou. D. Neudecker LANL Topics: Oxygen: R matrix calculations; planned (n,a) LANSCE exp Hydrogen scattering: Summary from

More information

Complete activation data libraries for all incident particles, all energies and including covariance data

Complete activation data libraries for all incident particles, all energies and including covariance data Complete activation data libraries for all incident particles, all energies and including covariance data Arjan Koning NRG Petten, The Netherlands Workshop on Activation Data EAF 2011 June 1-3 2011, Prague,

More information

Fundamental and Applied Nuclear Fission Research at LANL

Fundamental and Applied Nuclear Fission Research at LANL LA-UR-13-27602 Fundamental and Applied Nuclear Fission Research at LANL Patrick Talou T-2, Nuclear Physics Group, Los Alamos National Laboratory New Mexico, USA INT 13-3 Quantitative Large Amplitude Shape

More information

Status Report of WPEC Subgroup 7 April Nuclear Data Standards Coordinator: A. D. Carlson

Status Report of WPEC Subgroup 7 April Nuclear Data Standards Coordinator: A. D. Carlson Status Report of WPEC Subgroup 7 April 2005 Nuclear Data Standards Coordinator: A. D. Carlson Introduction The standards are the basis for the neutron reaction cross section libraries. It is important

More information

Monte Carlo Simulation for Statistical Decay of Compound Nucleus

Monte Carlo Simulation for Statistical Decay of Compound Nucleus CNR20, Prague, Czech Republic, Sep. 9 23, 20 Monte Carlo Simulation for Statistical Decay of Compound Nucleus T. Kawano, P. Talou, M.B Chadwick Los Alamos National Laboratory Compound Nuclear Reaction,

More information

Invited. Recent advances in the JENDL project. 1 Introduction. 2 Activities for general-purpose file

Invited. Recent advances in the JENDL project. 1 Introduction. 2 Activities for general-purpose file International Conference on Nuclear Data for Science and Technology 2007 DOI: 10.1051/ndata:07743 Invited Recent advances in the JENDL project K. Shibata 1,a, T. Nakagawa 1, T. Fukahori 1,O.Iwamoto 1,

More information

Resonance Evaluations of 235 U for the CIELO Project

Resonance Evaluations of 235 U for the CIELO Project Resonance Evaluations of 235 U for the CIELO Project L. Leal 1), A. Kahler 2), G. Noguere 3), O. Bouland 3), Y. Penneliau 3) 1) Oak Ridge National Laboratory 2) Los Alamos National Laboratory 3) CEA/Cadarache

More information

Covariance Generation using CONRAD and SAMMY Computer Codes

Covariance Generation using CONRAD and SAMMY Computer Codes Covariance Generation using CONRAD and SAMMY Computer Codes L. Leal a, C. De Saint Jean b, H. Derrien a, G. Noguere b, B. Habert b, and J. M. Ruggieri b a Oak Ridge National Laboratory b CEA, DEN, Cadarache

More information

VERIFICATION OFENDF/B-VII.0, ENDF/B-VII.1 AND JENDL-4.0 NUCLEAR DATA LIBRARIES FOR CRITICALITY CALCULATIONS USING NEA/NSC BENCHMARKS

VERIFICATION OFENDF/B-VII.0, ENDF/B-VII.1 AND JENDL-4.0 NUCLEAR DATA LIBRARIES FOR CRITICALITY CALCULATIONS USING NEA/NSC BENCHMARKS VERIFICATION OFENDF/B-VII.0, ENDF/B-VII.1 AND JENDL-4.0 NUCLEAR DATA LIBRARIES FOR CRITICALITY CALCULATIONS USING NEA/NSC BENCHMARKS Amine Bouhaddane 1, Gabriel Farkas 1, Ján Haščík 1, Vladimír Slugeň

More information

Nuclear Reaction Rates for Astrophysical Nucleosynthesis

Nuclear Reaction Rates for Astrophysical Nucleosynthesis Nuclear Reaction Rates for Astrophysical Nucleosynthesis Department of Physics, Central Michigan University, Mt. Pleasant, MI 48859, USA E-mail: palum1a@cmich.edu D. Galaviz Centro de Fisica Nuclear da

More information

Convergence Analysis and Criterion for Data Assimilation with Sensitivities from Monte Carlo Neutron Transport Codes

Convergence Analysis and Criterion for Data Assimilation with Sensitivities from Monte Carlo Neutron Transport Codes PHYSOR 2018: Reactor Physics paving the way towards more efficient systems Cancun, Mexico, April 22-26, 2018 Convergence Analysis and Criterion for Data Assimilation with Sensitivities from Monte Carlo

More information

Crawling Towards a (more) complete description of deuteron-induced reactions

Crawling Towards a (more) complete description of deuteron-induced reactions Crawling Towards a (more) complete description of deuteron-induced reactions B. V. Carlson 1, R. Capote 2 and M. Sin 3 1 Instituto Tecnológico de Aeronáutica, São José dos Campos SP, Brazil 2 NAPC-Nuclear

More information

Presentation for the CIELO Meeting of the NEA 9-11 May 2016 Paris, France. The Chinese work on 56 Fe

Presentation for the CIELO Meeting of the NEA 9-11 May 2016 Paris, France. The Chinese work on 56 Fe The Chinese work on 56 Fe Jing QIAN, Zhigang GE, Tingjin LIU, Hanlin LU, Xichao RUAN Guochang CHEN,Huanyu Huanyu ZHANG,Yangbo NIE China Nuclear Data Center(CNDC) China Institute of Atomic Energy(CIAE)

More information

R&D in Nuclear Data for Reactor Physics Applications in CNL (CNL = Canadian Nuclear Laboratories) D. Roubtsov

R&D in Nuclear Data for Reactor Physics Applications in CNL (CNL = Canadian Nuclear Laboratories) D. Roubtsov R&D in Nuclear Data for Reactor Physics Applications in CNL (CNL = Canadian Nuclear Laboratories) D. Roubtsov Nuclear Science Division, CNL, Chalk River, Canada -1- Improvement of TSL (Thermal Scattering

More information

Connecting fundamental models with nuclear reaction evaluations

Connecting fundamental models with nuclear reaction evaluations Connecting fundamental models with nuclear reaction evaluations G. P. A. Nobre National Nuclear Data Center Brookhaven National Laboratory Workshop at Institute for Nuclear Theory, March 13-17, 2017 Nuclear

More information

WPEC Sub group 34 Coordinated evaluation of 239 Pu in the resonance region

WPEC Sub group 34 Coordinated evaluation of 239 Pu in the resonance region WPEC Sub group 34 Coordinated evaluation of 239 Pu in the resonance region Coordinator C. De Saint Jean / Monitor R. D. McKnight Subgroup report Based on Contributions from ORNL/LANL and CEA Cadarache

More information

Assessment of the Unresolved Resonance Treatment for Cross-section and Covariance Representation

Assessment of the Unresolved Resonance Treatment for Cross-section and Covariance Representation Nuclear Science NEA/WPEC-32 NEA/NSC/WPEC/DOC(2011)430 International Evaluation Co-operation Volume 32 Assessment of the Unresolved Resonance Treatment for Cross-section and Covariance Representation A

More information

Considerations for Measurements in Support of Thermal Scattering Data Evaluations. Ayman I. Hawari

Considerations for Measurements in Support of Thermal Scattering Data Evaluations. Ayman I. Hawari OECD/NEA Meeting: WPEC SG42 Thermal Scattering Kernel S(a,b): Measurement, Evaluation and Application May 13 14, 2017 Paris, France Considerations for Measurements in Support of Thermal Scattering Data

More information

Testing of Nuclear Data Libraries for Fission Products

Testing of Nuclear Data Libraries for Fission Products Testing of Nuclear Data Libraries for Fission Products A.V. Ignatyuk, S.M. Bednyakov, V.N. Koshcheev, V.N. Manokhin, G.N. Manturov, and G.Ya. Tertuchny Institute of Physics and Power Engineering, 242 Obninsk,

More information

Analysis of the TRIGA Reactor Benchmarks with TRIPOLI 4.4

Analysis of the TRIGA Reactor Benchmarks with TRIPOLI 4.4 BSTRCT nalysis of the TRIG Reactor Benchmarks with TRIPOLI 4.4 Romain Henry Jožef Stefan Institute Jamova 39 SI-1000 Ljubljana, Slovenia romain.henry@ijs.si Luka Snoj, ndrej Trkov luka.snoj@ijs.si, andrej.trkov@ijs.si

More information

A dispersive optical model potential for nucleon induced reactions on 238 U and 232 Th nuclei with full coupling

A dispersive optical model potential for nucleon induced reactions on 238 U and 232 Th nuclei with full coupling EPJ Web of Conferences 4, 0005 (013) DOI: 10.1051/ epjconf/ 01340005 C Owned by the authors, published by EDP Sciences, 013 A dispersive optical model potential for nucleon induced reactions on 38 U and

More information

Nuclear Data Uncertainty Analysis in Criticality Safety. Oliver Buss, Axel Hoefer, Jens-Christian Neuber AREVA NP GmbH, PEPA-G (Offenbach, Germany)

Nuclear Data Uncertainty Analysis in Criticality Safety. Oliver Buss, Axel Hoefer, Jens-Christian Neuber AREVA NP GmbH, PEPA-G (Offenbach, Germany) NUDUNA Nuclear Data Uncertainty Analysis in Criticality Safety Oliver Buss, Axel Hoefer, Jens-Christian Neuber AREVA NP GmbH, PEPA-G (Offenbach, Germany) Workshop on Nuclear Data and Uncertainty Quantification

More information

Annals of Nuclear Energy

Annals of Nuclear Energy Annals of Nuclear Energy 73 (2014) 455 464 Contents lists available at ScienceDirect Annals of Nuclear Energy journal homepage: www.elsevier.com/locate/anucene Quasi-differential neutron scattering from

More information

Sensitivity Computation with Monte Carlo Methods

Sensitivity Computation with Monte Carlo Methods Sensitivity Computation with Monte Carlo Methods (Action C8, WPEC/Sg.39) E. Ivanov T. Ivanova WPEC/Sg. 39 Meeting Novembre 27-28, 2014 NEA, Issy-les-Moulineaux, 1 France General Remarks Objective of the

More information

Core Physics Second Part How We Calculate LWRs

Core Physics Second Part How We Calculate LWRs Core Physics Second Part How We Calculate LWRs Dr. E. E. Pilat MIT NSED CANES Center for Advanced Nuclear Energy Systems Method of Attack Important nuclides Course of calc Point calc(pd + N) ϕ dn/dt N

More information

Vladimir Sobes 2, Luiz Leal 3, Andrej Trkov 4 and Matt Falk 5

Vladimir Sobes 2, Luiz Leal 3, Andrej Trkov 4 and Matt Falk 5 A Study of the Required Fidelity for the Representation of Angular Distributions of Elastic Scattering in the Resolved Resonance Region for Nuclear Criticality Safety Applications 1 Vladimir Sobes 2, Luiz

More information

Status and future plan of JENDL. Osamu Iwamoto Nuclear Data Center Japan Atomic Energy Agency

Status and future plan of JENDL. Osamu Iwamoto Nuclear Data Center Japan Atomic Energy Agency Status and future plan of JENDL Osamu Iwamoto Nuclear Data Center Japan Atomic Energy Agency 1 Introduction JENDL-4.0 was released in 2010 with improving fissionproduct, minor-actinide, and covariance.

More information

Introduction to Nuclear Engineering

Introduction to Nuclear Engineering 2016/9/27 Introduction to Nuclear Engineering Kenichi Ishikawa ( ) http://ishiken.free.fr/english/lecture.html ishiken@n.t.u-tokyo.ac.jp 1 References Nuclear Physics basic properties of nuclei nuclear

More information

Nuclear Data Activities in the IAEA-NDS

Nuclear Data Activities in the IAEA-NDS Nuclear Data Activities in the IAEA-NDS R.A. Forrest Nuclear Data Section Department of Nuclear Sciences and Applications Outline NRDC NSDD EXFOR International collaboration CRPs DDPs Training Security

More information

Nuclear data uncertainty propagation using a Total Monte Carlo approach

Nuclear data uncertainty propagation using a Total Monte Carlo approach Nuclear data uncertainty propagation using a Total Monte Carlo approach Arjan Koning* & and Dimitri Rochman* *NRG Petten, The Netherlands & Univ. Uppsala Workshop on Uncertainty Propagation in the Nuclear

More information

Nuclear Data Uncertainty Quantification for Applications in Energy, Security, and Isotope Production

Nuclear Data Uncertainty Quantification for Applications in Energy, Security, and Isotope Production Nuclear Data Uncertainty Quantification for Applications in Energy, Security, and Isotope Production I. Gauld M. Williams M. Pigni L. Leal Oak Ridge National Laboratory Reactor and Nuclear Systems Division

More information

Present Status and Plans of JENDL FP Data Evaluation Project

Present Status and Plans of JENDL FP Data Evaluation Project Present Status and Plans of JENDL FP Data Evaluation Project KAWANO Toshihiko and FP Nuclear Data Evaluation Working Group 1 Interdisciplinary Graduate School of Engineering Sciences, Kyushu University

More information

Office of Nonproliferation and Verification Research and Development University and Industry Technical Interchange (UITI2011) Review Meeting

Office of Nonproliferation and Verification Research and Development University and Industry Technical Interchange (UITI2011) Review Meeting Office of Nonproliferation and Verification Research and Development niversity and Industry Technical Interchange (ITI2011) Review Meeting Modeling of SNM Fission Signatures and December 7, 2011 Gennady

More information

Investigation of Nuclear Data Accuracy for the Accelerator- Driven System with Minor Actinide Fuel

Investigation of Nuclear Data Accuracy for the Accelerator- Driven System with Minor Actinide Fuel Investigation of Nuclear Data Accuracy for the Accelerator- Driven System with Minor Actinide Fuel Kenji Nishihara, Takanori Sugawara, Hiroki Iwamoto JAEA, Japan Francisco Alvarez Velarde CIEMAT, Spain

More information

Neutronic analysis of SFR lattices: Serpent vs. HELIOS-2

Neutronic analysis of SFR lattices: Serpent vs. HELIOS-2 Neutronic analysis of SFR lattices: Serpent vs. HELIOS-2 E. Fridman 1, R. Rachamin 1, C. Wemple 2 1 Helmholtz Zentrum Dresden Rossendorf 2 Studsvik Scandpower Inc. Text optional: Institutsname Prof. Dr.

More information

High precision neutron inelastic cross section measurements

High precision neutron inelastic cross section measurements High precision neutron inelastic cross section measurements A. Olacel, C. Borcea, M. Boromiza, A. Negret IFIN-HH, DFN Outline The experimental setup GELINA GAINS Data analysis algorithm. Monte Carlo simulations

More information

Statistical Theory for the Beta-Delayed Neutron and Gamma-Ray Emission

Statistical Theory for the Beta-Delayed Neutron and Gamma-Ray Emission Statistical Theory for the Beta-Delayed Neutron and Gamma-Ray Emission T. Kawano, P Möller Theoretical Division, Los Alamos National Laboratory LA-UR-13-21895 Slide 1 Combining QRPA Calculation and Statistical

More information

Nuclear Cross-Section Measurements at the Manuel Lujan Jr. Neutron Scattering Center

Nuclear Cross-Section Measurements at the Manuel Lujan Jr. Neutron Scattering Center 1 Nuclear Cross-Section Measurements at the Manuel Lujan Jr. Neutron Scattering Center M. Mocko 1, G. Muhrer 1, F. Tovesson 1, J. Ullmann 1 1 LANSCE, Los Alamos National Laboratory, Los Alamos NM 87545,

More information

Sensitivity and Uncertainty Analysis of the k eff and b eff for the ICSBEP and IRPhE Benchmarks

Sensitivity and Uncertainty Analysis of the k eff and b eff for the ICSBEP and IRPhE Benchmarks Sensitivity and Uncertainty Analysis of the k eff and b eff for the ICSBEP and IRPhE Benchmarks ANDES Workpackage N : 3, Deliverable D3.3 Ivo Kodeli Jožef Stefan Institute, Slovenia ivan.kodeli@ijs.si

More information

VorobyevA.S., ShcherbakovO.A., GagarskiA.M., Val ski G.V., Petrov G.A.

VorobyevA.S., ShcherbakovO.A., GagarskiA.M., Val ski G.V., Petrov G.A. Investigation of the Prompt Neutron Emission Mechanism in Low Energy Fission of 233, 235 U(n th, f) and 252 Cf(sf) VorobyevA.S., ShcherbakovO.A., GagarskiA.M., Val ski G.V., Petrov G.A. Petersburg Nuclear

More information

Correlations in nuclear data from integral constraints

Correlations in nuclear data from integral constraints WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN D. Rochman 1, E. Bauge 2 and A.J. Koning 3 1 PSI, 2 CEA DAM DIF, France, 3 IAEA Correlations in nuclear data from integral constraints JEFDOC-1897 JEFF meeting, 20

More information

Present Status of the JENDL Project. Osamu IWAMOTO and Kenji YOKOYAMA Japan Atomic Energy Agency

Present Status of the JENDL Project. Osamu IWAMOTO and Kenji YOKOYAMA Japan Atomic Energy Agency Present Status of the JENDL Project Osamu IWAMOTO and Kenji YOKOYAMA Japan Atomic Energy Agency Japanese Nuclear Data Committee Japan Atomic Energy Agency JNDC (chaired by N. Yamano, Univ. of Fukui) Subcommittee

More information

PROGRESS OF NUCLEAR DATA MEASUREMENT IN CHINA

PROGRESS OF NUCLEAR DATA MEASUREMENT IN CHINA PROGRESS OF NUCLEAR DATA MEASUREMENT IN CHINA (2011-2012 ) GE Zhigang RUAN Xichao China Nuclear Data Key Laboratory China Nuclear Data Center(CNDC) China Committee of Nuclear Data(CCND) China Institute

More information

Future research program on prompt γ-ray emission in nuclear fission

Future research program on prompt γ-ray emission in nuclear fission Future research program on prompt γ-ray emission in nuclear fission Robert Billnert, Aleksandar Dragic, Angélique Gatera, Alf Göök, Pierre Halipré, Mattieu Lebois, Andreas Oberstedt, Stephan Oberstedt,

More information

Determination of neutron induced fission fragment spin distribution after neutron evaporation

Determination of neutron induced fission fragment spin distribution after neutron evaporation Determination of neutron induced fission fragment spin distribution after neutron evaporation A. Chebboubi, G. Kessedjian, C. Sage, O. Méplan LPSC, Université Grenoble-Alpes, CNRS/IN2P3, F-38026 Grenoble,

More information

Bayesian Unified Monte Carlo Method for Evaluating and Utilizing Nuclear Reaction Data

Bayesian Unified Monte Carlo Method for Evaluating and Utilizing Nuclear Reaction Data Bayesian Unified Monte Carlo Method for Evaluating and Utilizing Nuclear Reaction Data Donald Smith, Argonne Associate of Seville Staffing LLC Roberto Capote, International Atomic Energy Agency Denise

More information

Database and Data Evaluation Activities by the IAEA A+M Data Unit

Database and Data Evaluation Activities by the IAEA A+M Data Unit Database and Data Evaluation Activities by the A+M Data Unit Bas Braams and Hyun Chung Second Research Coordination Meeting of the CRP on A+M Data for Hydrogen and Helium in Fusion Plasma Vienna, 3-5 July

More information

Study of prompt neutron emission spectra in fast neutron induced fission of 238 U and 232 Th and 30 kev neutron induced fission on 235 U

Study of prompt neutron emission spectra in fast neutron induced fission of 238 U and 232 Th and 30 kev neutron induced fission on 235 U Study of prompt neutron emission spectra in fast neutron induced fission of 238 U and 232 Th and 30 kev neutron induced fission on 235 U S. Appannababu 1, J. Praena 2, P.F. Mastinu 1, T. Marchi 1, V.V.

More information

A TEMPERATURE DEPENDENT ENDF/B-VI.8 ACE LIBRARY FOR UO2, THO2, ZIRC4, SS AISI-348, H2O, B4C AND AG-IN-CD

A TEMPERATURE DEPENDENT ENDF/B-VI.8 ACE LIBRARY FOR UO2, THO2, ZIRC4, SS AISI-348, H2O, B4C AND AG-IN-CD 2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 A TEMPERATURE

More information