324
Views
0
CrossRef citations to date
0
Altmetric
TECHNICAL MATERIAL

Validation of MVP-II with JENDL-4.0, ENDF/B-VII.1, and JEFF-3.2 through HTC critical experiments

Pages 661-667 | Received 06 Mar 2019, Accepted 09 Apr 2019, Published online: 29 Apr 2019

References

  • Fernex F, Ivanova T, Bernard F, et al. HTC experimental program: validation and calculational analysis. Nucl Sci Eng. 2009;162:1–24.
  • Mueller E, Elam R, Fox B Evaluation of the French Haut Taux de Combustion (HTC) critical experiment data. U.S.: NRC; 2008, (NUREG/CR-6979).
  • SCALE: a modular code system for performing standardized computer analyses for licensing evaluations. Tennessee (The U.S.): ORNL; 2005, (ORNL/TM-2005/39).
  • U.S. NRC. Interim staff guidance – 8 Revision 3, Division of spent fuel storage and transportation. Washington DC, U.S.: NRC; 2012.
  • Nagaya Y, Okumura K, Mori T, et al. MVP/GMVP II: general purpose monte carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods. Tokai-mura (Japan): Japan Atomic Energy Agency; 2005, (JAERI-1348) [in Japanese, .
  • Shibata K, Iwamoto O, Nakagawa T, et al. JENDL-4.0: a new library for nuclear science and engineering. J Nucl Sci Technol. 2011;48:1–30.
  • Chadwick M, Herman M, Obloˇzinsky P, et al. ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data. Nucl Data Sheets. 2011;112(12):2887–2996.
  • The JEFF team. JEFF-3.2: evaluated nuclear data library. 2014. Available from: http://www.oecd-nea.org/dbdata/jeff/
  • Scale: a comprehensive modeling and simulation suite for nuclear safety analysis and design. Tennessee, U.S.: ORNL; 2009, (ORNL/TM-2005/39).
  • NEA Nuclear Science Committee, International handbook of evaluated criticality safety benchmark experiments. Paris (France): OECD/NEA; 2006, (NEA/NSC/DOC (95)03).
  • Yamamoto T, Sakai T. Feedback on neutron capture cross sections of 238Pu and 241Am from analysis of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments. J Nucl Sci Technol. 2016;53:1235–1242.
  • Nakajima K, Sano T, Yamamoto T, Validation of 241Am capture cross section through integral test using criticality data of light-water moderated MOX cores. Proceeding of the Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4, Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology; 2015;71:237–243.

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.