3-D extension C5G7 MOX benchmark results using CHAPLET-3D

Progress in Nuclear Energy

Volumn 48, Issue 5, 2006, Pages 439-444

  Kosaka, Shinya ^a  

^a TEPCO SYSTEMS CORPORATION   (Japan)

Author keywords

C5G7 MOX benchmark; CHAPLET 3D; MOC

Indexed keywords

BENCHMARKING; CODES (SYMBOLS); COMPUTATIONAL METHODS; EIGENVALUES AND EIGENFUNCTIONS; MONTE CARLO METHODS; PROBLEM SOLVING;

C5G7 MOX BENCHMARK; CHAPLET-3D; MOC;

NUCLEAR ENERGY;

EID: 33746208820     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2006.01.004     Document Type: Article

References (6)

1. Halsall M.J. CACTUS, A Characteristics Solution to the Neutron Transport Equations in Complicated Geometries. AEEW-R1291 (1980), UKAEA, Winfrith
2. Kosaka S., et al. Transport theory calculation for a heterogeneous multi-assembly problem by characteristics method with direct neutron path linking technique. J. Nucl. Sci. Technol. 37 12 (2000) 1015
3. Kosaka S., et al. Verification of 3D heterogeneous core transport calculation utilizing non-linear iteration technique. J. Nucl. Sci. Technol. 41 (2004) 645
4. Smith K. Nodal method storage reduction by nonlinear iteration. Trans. Am. Nucl. Soc. 44 (1984) 265
5. Smith M.A., et al., 2003a. Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation: A 2-D/3-D MOX Fuel Assembly Benchmark. OECD/NEA report, NEA/NSC/DOC(2003)16.
6. Smith, M.A., et al., 2003b. Benchmark Specification for Deterministic MOX Fuel Assembly Transport Calculations without Spatial Homogenisation (3-D Extension C5G7 MOX). OECD/NEA Report, NEA/NSC/DOC(2003)6.