Ultra-fine-group resonance treatment using equivalent Dancoff-factor cell model in lattice physics code GALAXY

References

• Yamaji K, Matsumoto H, Kirimura K, et al. Development of a new lattice physics code GALAXY for flexible geometry representation in next generation core analysis system. Trans Am Nucl Soc. 2007;97:573–574. [ CD-ROM].
   Google Scholar
• Koike H, Yamaji K, Kirimura K, et al. Advanced resonance self-shielding method for gray resonance treatment in lattice physics code GALAXY. J Nucl Sci Technol. 2012;49:725–747.
   Web of Science ®Google Scholar
• Sato D, Tsubota S, Yamaji K, et al. A new robust cross section representation methodology for PWR core simulator. Proceedings of International Conference on physics of Reactors (PHYSOR 2010). 2010 May 9–14. Pittsburgh, PA, USA. [ CD-ROM]
   Google Scholar
• Kosaka S, Kirimura K, Yamaji K, et al. Development of MHI core analysis code package based on GalaxyCosmo-S. Trans Am Nucl Soc. 2013;109:1348–1350. [ CD-ROM].
   Google Scholar
• Kirimura K, Yamaji K, Kosaka S, et al. Verification and validation of MHI nuclear design code system GalaxyCosmo-S. Trans Am Nucl Soc. 2013; 109: 1336–1338. [ CD-ROM].
   Google Scholar
• Sugimura N, Yamamoto A. Resonance treatment based on ultra-fine-group spectrum calculation in the AEGIS code. J Nucl Sci Technol. 2007;44:958–966.
   Web of Science ®Google Scholar
• Ishiguro Y. PEACO-II: A code for calculation of effective cross section in heterogeneous systems. Ibaraki: Japanese Atomic Energy Research Institute (JAERI); 1971. JAERI-M 5527.
   Google Scholar
• Williams M, Asgari M. Computation of continuous-energy neutron spectra with discrete ordinates transport theory. Nucl Sci Eng. 1995;121:173–201.
   Web of Science ®Google Scholar
• Yamamoto A. Evaluation of background cross section for heterogeneous and complicated geometry by the enhanced neutron current method. J Nucl Sci Technol. 2008;45:1287–1292.
   Web of Science ®Google Scholar
• Sugimura N, Yamamoto A. Evaluation of Dancoff factors in complicated geometry using the method of characteristics. J Nucl Sci Technol. 2006;43:1182–1187.
   Web of Science ®Google Scholar
• Tatsumi M, Ohoka Y, Sugimura N, et al. [Core Analysis of a Commercial PWR with AEGIS/SCOPE2] [CD-ROM]. Proceedings of 2008 Annual Meeting of AESJ;2008 March 26-28. Osaka (Japan). L36 [ in Japanese].
   Google Scholar
• Stamm'ler RJJ, Abbate MJ. Methods of steady-state reactor physics in nuclear design. London: Academic Press; 1983.
   Google Scholar
• Askew R. A characteristics formulation of the neutron transport equation in complicated geometries. Winfrith: Atomic Energy Authority; 1972. AEEW-M1108.
   Google Scholar
• Goldstein R, Cohen E R. Theory of resonance absorption of neutrons. Nucl Sci Eng. 1962;13:132–140.
   Web of Science ®Google Scholar
• Ouisloumen M, Sanchez R. A model for neutron scattering off heavy isotopes that accounts for thermal agitation effects. Nucl Sci Eng. 1990;107:189–200.
   Web of Science ®Google Scholar
• Lee D, Smith K, Rhodes J. The impact of 238 U resonance elastic scattering approximations on thermal reactor Doppler reactivity. Ann Nucl Energ. 2009;36(3):274–280.
   Web of Science ®Google Scholar
• Hebert A. A consistent technique for the pin-by-pin homogenization of a pressurized water reactor assembly. Nucl Sci Eng. 1993;113:227–238.
   Web of Science ®Google Scholar
• Sartori E. Standard energy group structures of cross section libraries for reactor shielding, reactor cell and fusion neutronics applications: VITAMIN-J, ECCO-33, ECCO-2000 and XMAS, JEF/DOC-315, Revision 3. Gif-sur-Yvette: NEA Data Bank; 1990.
   Google Scholar
• Chadwick MB, Oblozinsky P, Herman M, et al. ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology. Nucl Data Sheets. 2006;107:2931–3060.
   Google Scholar
• Macfarlane RE, Kahler AC. Methods for Processing ENDF/B-VII with NJOY. Nucl Data Sheets. 2010;11:2739–2890.
   Google Scholar
• Hazama T, Chiba G, Sugino K. Development of a fine and ultra-fine group cell calculation code SLAROM-UF for fast reactor analyses. J Nucl Sci Technol. 2006;43:908–918.
   Web of Science ®Google Scholar
• 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. Ibaraki: Japanese Atomic Energy Research Institute (JAERI); 2005. JAERI 1348.
   Google Scholar
• Reload startup physics tests for pressurized water reactors. La Grange Park: American Nuclear Society (ANS); 2011. ANSI/ANS-19.6.1-2011.
   Google Scholar