-
1
-
-
65449141025
-
Fission spectrum related uncertainties
-
Prague, Czech Republic, October 16-18
-
G. Aliberti, I. Kodeli, G. Palmiotti, M. Salvatores, Fission spectrum related uncertainties, in: Proceedings of the NEMEA-4 Neutron Measurements, Evaluations and Applications, Prague, Czech Republic, October 16-18, 2007, 2008, pp. 135-138.
-
(2007)
Proceedings of the NEMEA-4 Neutron Measurements, Evaluations and Applications
, pp. 135-138
-
-
Aliberti, G.1
Kodeli, I.2
Palmiotti, G.3
Salvatores, M.4
-
2
-
-
72049129905
-
-
M. Salvatores (Co-ordinator), OECD/NEA WPEC Subgroup 26 Final Report: Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations (APPENDIX M: I. Kodeli, M. Ishikawa, G. Aliberti, Evaluation of Fission Spectra Uncertainty and their Propagation), NEA/WPEC-26, OECD, Paris, 2008, ISBN 978-92-64-99053-1.
-
M. Salvatores (Co-ordinator), OECD/NEA WPEC Subgroup 26 Final Report: Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations (APPENDIX M: I. Kodeli, M. Ishikawa, G. Aliberti, Evaluation of Fission Spectra Uncertainty and their Propagation), NEA/WPEC-26, OECD, Paris, 2008, ISBN 978-92-64-99053-1.
-
-
-
-
3
-
-
65449149150
-
Ambiguity in coding the covariances of emission spectra in MF35 of ENDF-6 files
-
Available online at
-
A. Trkov, Ambiguity in coding the covariances of emission spectra in MF35 of ENDF-6 files, request addressed at CSEWG meeting, 2007. Available online at 〈http://www.nndc.bnl.gov/proceedings/2007csewgusndp/〉.
-
(2007)
request addressed at CSEWG meeting
-
-
Trkov, A.1
-
4
-
-
72049131511
-
-
Y. Nagaya, Private communication on uncertainty of effective multiplication factor with respect to fission spectrum, Japan Atomic Energy Agency, 19, November 2007.
-
Y. Nagaya, Private communication on uncertainty of effective multiplication factor with respect to fission spectrum, Japan Atomic Energy Agency, 19, November 2007.
-
-
-
-
5
-
-
72049093433
-
-
Private communication on the equivalence between the SAGEP sensitivity method and the ENDF-102 formalism for the correction of fission spectra covariance matrix, in: IAEA/NEA, 30, November 2007
-
I. Kodeli, Private communication on the equivalence between the SAGEP sensitivity method and the ENDF-102 formalism for the correction of fission spectra covariance matrix, in: IAEA/NEA, vol. 30, November 2007.
-
-
-
Kodeli, I.1
-
6
-
-
72049118404
-
-
Private communication. Comments on response parameter uncertainty due to fission spectrum uncertainties, ANL, 4 December
-
W.S. Yang, Private communication. Comments on response parameter uncertainty due to fission spectrum uncertainties, ANL, 4 December 2007.
-
(2007)
-
-
Yang, W.S.1
-
9
-
-
72049103379
-
235U fission neutron emission
-
Workshop, Borovets, Bulgaria, 25-28 October
-
235U fission neutron emission, in: Proceedings of the NEMEA-3 Workshop, Borovets, Bulgaria, 25-28 October 2006.
-
(2006)
Proceedings of the NEMEA-3
-
-
Kornilov, N.V.1
Hambsch, F.-J.2
Fabry, I.3
Oberstedt, S.4
Simakov, S.P.5
-
11
-
-
33947156628
-
-
Chadwick M.B., Obložinsky P., Herman M., Greene N.M., McKnight R.D., Smith D.L., Young P.G., MacFarlane R.E., Hale G.M., Frankle S.C., Kahler A.C., Kawano T., Little R.C., Madland D.G., Moller P., Mosteller R.D., Page P.R., Talou P., Trellue H., White M.C., et al. Nucl. Data Sheets 107 (2006) 2931
-
(2006)
Nucl. Data Sheets
, vol.107
, pp. 2931
-
-
Chadwick, M.B.1
Obložinsky, P.2
Herman, M.3
Greene, N.M.4
McKnight, R.D.5
Smith, D.L.6
Young, P.G.7
MacFarlane, R.E.8
Hale, G.M.9
Frankle, S.C.10
Kahler, A.C.11
Kawano, T.12
Little, R.C.13
Madland, D.G.14
Moller, P.15
Mosteller, R.D.16
Page, P.R.17
Talou, P.18
Trellue, H.19
White, M.C.20
more..
-
15
-
-
72049091433
-
-
R.E. Maerker, J.J. Wagschal, B.L. Broadhead, Development and demonstration of an advanced methodology for LWR dosimetry applications. (Section 7), EPRI NP-2188 (December 1981), Report available in ZZ DOSCOV, 24-Group Covariance Data Library from ENDF/B-V for Dosimetry Calculation, DLC-0090 package of NEA Data Bank collection 〈http://www.nea.fr/abs/html/dlc-0090.html〉.
-
R.E. Maerker, J.J. Wagschal, B.L. Broadhead, Development and demonstration of an advanced methodology for LWR dosimetry applications. (Section 7), EPRI NP-2188 (December 1981), Report available in ZZ DOSCOV, 24-Group Covariance Data Library from ENDF/B-V for Dosimetry Calculation, DLC-0090 package of NEA Data Bank collection 〈http://www.nea.fr/abs/html/dlc-0090.html〉.
-
-
-
-
16
-
-
72049109914
-
-
SCALE: a modular code system for performing standardized computer analyses for licensing evaluations, ORNL/TM-2005/39, version 5.1, vols. I-III, November 2006
-
SCALE: a modular code system for performing standardized computer analyses for licensing evaluations, ORNL/TM-2005/39, version 5.1, vols. I-III, November 2006.
-
-
-
-
18
-
-
72049129653
-
-
G. Chiba, ERRORJ: a code to process neutron-nuclide reaction cross section covariance, version 2.3, JAEA-Data/Code 2007-007, 2007
-
G. Chiba, ERRORJ: a code to process neutron-nuclide reaction cross section covariance, version 2.3, JAEA-Data/Code 2007-007, 2007.
-
-
-
-
19
-
-
84868488052
-
The NJOY nuclear data processing system, LA-12740-M, Los Alamos National Laboratory
-
RSICC CODE PACKAGE PSR-368
-
R.E. MacFarlane, D.W. Muir, The NJOY nuclear data processing system, LA-12740-M, Los Alamos National Laboratory, 1994. RSICC CODE PACKAGE PSR-368, 1999.
-
(1994)
-
-
MacFarlane, R.E.1
Muir, D.W.2
-
20
-
-
72049113283
-
-
Cross Section Evaluation Working Group, in: M. Herman (Ed.), ENDF-6 Formats Manual; Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VII, Document ENDF-102, Report BNL-NCS-44945-05, Brookhaven National Laboratory, USA, 2005.
-
Cross Section Evaluation Working Group, in: M. Herman (Ed.), ENDF-6 Formats Manual; Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VII, Document ENDF-102, Report BNL-NCS-44945-05, Brookhaven National Laboratory, USA, 2005.
-
-
-
-
23
-
-
33845740106
-
SINBAD shielding benchmark experiments status and planned activities
-
Carlsbad, NM, USA, April 3-6 2006 available online at
-
I. Kodeli, E. Sartori, B. Kirk, SINBAD shielding benchmark experiments status and planned activities, in: Proceedings of the ANS 14th Biennial Topical Meeting of the Radiation Protection and Shielding Division, Carlsbad, NM, USA, April 3-6 2006 (available online at 〈http://www.nea.fr/html/science/shielding/sinbad/sinbadis.htm〉 ).
-
Proceedings of the ANS 14th Biennial Topical Meeting of the Radiation Protection and Shielding Division
-
-
Kodeli, I.1
Sartori, E.2
Kirk, B.3
-
24
-
-
72049114666
-
-
I. Kodeli, Etudes des incertitudes sur la fluence dans les cuves des REP, ajustement des données de base, Ph.D. Theses, Université Paris XI-Orsay, 1991.
-
I. Kodeli, Etudes des incertitudes sur la fluence dans les cuves des REP, ajustement des données de base, Ph.D. Theses, Université Paris XI-Orsay, 1991.
-
-
-
-
25
-
-
72049108878
-
-
A. Hara, T. Takeda, Y. Kikuchi, SAGEP: two-dimensional sensitivity analysis code based on generalized perturbation theory, JAERI-M, 84-027, 1984 (in Japanese).
-
A. Hara, T. Takeda, Y. Kikuchi, SAGEP: two-dimensional sensitivity analysis code based on generalized perturbation theory, JAERI-M, 84-027, 1984 (in Japanese).
-
-
-
-
28
-
-
72049091983
-
-
IRPhE Handbook, International Handbook of Evaluated Reactor Physics Benchmark Experiments, NEA-1765/05 package, OECD/NEA Data Bank, 2009.
-
IRPhE Handbook, International Handbook of Evaluated Reactor Physics Benchmark Experiments, NEA-1765/05 package, OECD/NEA Data Bank, 2009.
-
-
-
-
29
-
-
72049089186
-
-
Prediction of Neutron Embrittlement in the Reactor Pressure Vessel, VENUS-1 and VENUS-3 Benchmarks, OECD NEA, 2000.
-
Prediction of Neutron Embrittlement in the Reactor Pressure Vessel, VENUS-1 and VENUS-3 Benchmarks, OECD NEA, 2000.
-
-
-
-
30
-
-
72049092899
-
-
W.A. Rhoades, et al., DOORS3.2, one-, two-, three-dimensional discrete ordinates neutron/photon transport code system, CCC-650, RSICC, Oak Ridge National Laboratory, 1998.
-
W.A. Rhoades, et al., DOORS3.2, one-, two-, three-dimensional discrete ordinates neutron/photon transport code system, CCC-650, RSICC, Oak Ridge National Laboratory, 1998.
-
-
-
-
32
-
-
72049101163
-
-
Benchmark on the KRITZ-2 LEU and MOX critical experiments, Final Report, NEA/NSC/DOC, ISBN 92-64-02298-8, OCDE 2006
-
Benchmark on the KRITZ-2 LEU and MOX critical experiments, Final Report, NEA/NSC/DOC(2005)24, ISBN 92-64-02298-8, OCDE 2006.
-
(2005)
, pp. 24
-
-
-
33
-
-
72049111219
-
-
E. Ivanov, SNEAK 7A and 7B Pu-Fuelled Fast Critical Assemblies in the Karlsruhe Fast Critical Facility, Internal Reviewers V. Mastrangelo, I. Kodeli, NEA/NSC/DOC(2006)1, LMFR, SNEAK-LMFR-EXP-001, CRIT-SPEC-COEF-KIN-RRATE-MISC (March 2008), Available in IRPhE Handbook from 〈http://www.nea.fr〉.
-
E. Ivanov, SNEAK 7A and 7B Pu-Fuelled Fast Critical Assemblies in the Karlsruhe Fast Critical Facility, Internal Reviewers V. Mastrangelo, I. Kodeli, NEA/NSC/DOC(2006)1, LMFR, SNEAK-LMFR-EXP-001, CRIT-SPEC-COEF-KIN-RRATE-MISC (March 2008), Available in IRPhE Handbook from 〈http://www.nea.fr〉.
-
-
-
-
34
-
-
72049088208
-
-
Chicago, IL, April 25-29, on CD-ROM, American Nuclear Society, Lagrange Park, IL
-
S.J. Kim, I. Kodeli, E. Sartori, Analysis of SNEAK-7A and 7B Critical Benchmarks using 3-D Deterministic Transport and Sensitivity Analysis Methods, PHYSOR 2004-The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, IL, April 25-29, 2004, on CD-ROM, American Nuclear Society, Lagrange Park, IL, 2004.
-
(2004)
Analysis of SNEAK-7A and 7B Critical Benchmarks using 3-D Deterministic Transport and Sensitivity Analysis Methods, PHYSOR 2004-The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments
-
-
Kim, S.J.1
Kodeli, I.2
Sartori, E.3
-
35
-
-
72049125571
-
-
R.E. Alcouffe, et al., DANTSYS3.0-A Diffusion Accelerated, Neutron-Particle Transport System, LA-12969-M, Los Alamos National Laboratory, 1995.
-
R.E. Alcouffe, et al., DANTSYS3.0-A Diffusion Accelerated, Neutron-Particle Transport System, LA-12969-M, Los Alamos National Laboratory, 1995.
-
-
-
-
37
-
-
84871836969
-
Neutron cross-section covariance data in multigroup form and procedure for interpolation to users' group structures for uncertainty analysis applications
-
Marseille
-
I. Kodeli, E. Sartori, Neutron cross-section covariance data in multigroup form and procedure for interpolation to users' group structures for uncertainty analysis applications, in: Proceedings of the PHYSOR'90 Conference, Marseille, 1990.
-
(1990)
Proceedings of the PHYSOR'90 Conference
-
-
Kodeli, I.1
Sartori, E.2
-
38
-
-
63449098312
-
-
NEA/NSC/DOC
-
K. Ivanov, M. Avramova, I. Kodeli, E. Sartori, Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of LWRs, Specification and Support Data for the Neutronics Cases (Phase I), vol. I, NEA/NSC/DOC(2007)23, 2007.
-
(2007)
Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of LWRs, Specification and Support Data for the Neutronics Cases (Phase I)
, vol.1
, pp. 23
-
-
Ivanov, K.1
Avramova, M.2
Kodeli, I.3
Sartori, E.4
|