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Technical Material

Analysis of measured isotopic compositions by CASMO5 coupled with a JENDL-4.0 base library for irradiated fuel of light water reactors

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Pages 391-403 | Received 04 Oct 2016, Accepted 25 Nov 2016, Published online: 13 Jan 2017

References

  • Rhodes J, Smith K, Lee D. CASMO-5 development and application. Proc. PHYSOR-2006, ANS Topical Meeting on Reactor Physics; 2006 Sep 10–14; Vancouber (Canada). [ CD-ROM].
  • Bahadir T, Lindahl S. Studsvik's next generation nodal code SIMULATE-5. Proc. Advances in Nuclear Fuel Management IV (ANFM 2009); 2009 April 12–15; Hilton Head Island (USA). [ CD-ROM].
  • Shibata K, Iwamoto O, Nakagawa T, et al. JENDL-4.0: a new library for nuclear science and engineering. J. Nucl. Sci. Technol. 2011 Jan;48:1–30.
  • Rhodes J, Gheorghiu N, Ferrer R. CASMO5 JENDL-4.0 and ENDF/B-VII.1beta4 libraries. Proc. PHYSOR 2012-Advancees in Reactor Physics, Industry and Education; 2012 April 15–20; Knoxville (USA). [ CD-ROM].
  • Spent nuclear fuel assay data for isotopic validation. Nuclear Science. Nuclear Energy Agency, OECD; 2011; NEA/NSC/WPNCS/DOC(2011)5.
  • Gauld IC, Ilas G, and Radulescu G. Uncertainties in predicted isotopic compositions for high burnup PWR spent nuclear fuel. Tennessee: Oak Ridge National Laboratory; 2011, Report no. NUREG/CR-7012, ORNL/TM-2010/41.
  • Yamamoto T. Validation of ORIGEN2 coupled with JENDL-4.0 base libraries for isotopic compositions of irradiated light water reactor fuels. Proc. PHYSOR 2014- The Role of Reactor Physics Toward a Sustainable Future; 2014 September 20–October 3; Kyoto (Japan). [ CD-ROM].
  • Nakahara Y, Suyama K, Inagawa J, et al. Nuclide composition benchmark data set for verifying burnup codes on spent light water reactor fuel. Nucl. Technol. 2002;137:111–126.
  • Suyama K, Murazaki M, Ohkubo K, et al. Re-evaluation of assay data of spent nuclear fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems.Ann Nucl Energy. 2001;38:930–941.
  • Yamamoto T, Suzuki M, Ando Y et al. Analysis of measured isotopic compositions of high-burnup PWR MOX and UO2 fuels in the MALIBU program. J Nucl Sci Technol. 2012;49:910–925.
  • Yamamoto T, Ando Y, Hayashi Y et al. Analysis of core physics experiments on fresh and irradiated PWR UO2 fuels in the REBUS program. J Nucl Sci Technol. 2011;48:1025–1045.
  • Primm III R.T. ARIANE international programme final report. Tennessee: Oak Ridge National Laboratory; 2003, Report no. ORNL/SUB/97-XSV750-1.
  • Ilas G, Gauld IC Analysis of experimental data for high-burnup PWR spent fuel isotopic Validation-Vandelos II reactor. Tennessee: Oak Ridge National Laboratory; 2011, Report no. NUREG/CR-7013, ORNL/TM-2009/321.
  • Suzuki M, Yamamoto T, Fukaya H, et al. Lattice physics analysis of measured isotopic compositions of irradiated BWR 9 × 9 UO2 fuel. J Nucl Sci Technol. 2013;50:1161–1176.
  • Yamamoto T, Kanayama Y. Lattice physics analysis of burnups and isotope inventories of U, Pu, and Nd of irradiated BWR 9×9-9 UO2 fuel assemblies. J. Nucl. Sci. Technol. 2008; 45: 547–566.
  • Smith HJ, Gauld IC, Mertyrek U. Analysis of experimental data for high burnup BWR spent fuel isotopic validation – SVEA-96 and GE14 assembly designs. Tennessee: Oak Ridge National Laboratory; 2013, Report no. NUREG/CR-7162, ORNL/TM-2013.
  • Ando Y, Yamamoto T, Sugou Y. Analysis of measured isotopic compositions of high-burnup BWR MOX fuel. J Nucl Sci Technol. 2011;48:384–397.
  • Standard test method for atom percent fission in uranium and plutonium fuel (neodymium-148 method). PA: ASTM international; 2005, Report no. ASTM E321-96.

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