Solution of the C5G7MOX benchmark three-dimensional extension problems by the DeCART direct whole core calculation code

Progress in Nuclear Energy

Volumn 48, Issue 5, 2006, Pages 456-466

  Cho, Jin Young ^a   Joo, Han Gyu ^b  

^a Korea Atomic Energy Research Institute   (South Korea)

^b Seoul National University   (South Korea)

Author keywords

C5G7MOX 3 D extension; CMFD; DeCART; Direct whole core calculation; MOC

Indexed keywords

BENCHMARKING; EIGENVALUES AND EIGENFUNCTIONS; ERROR ANALYSIS; FINITE DIFFERENCE METHOD; NUCLEAR FUELS; PROBLEM SOLVING;

C5G7MOX 3-D EXTENSION; CMFD; DECART; DIRECT WHOLE CORE CALCULATION; MOC;

NUCLEAR ENERGY;

EID: 33746208833     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2006.01.006     Document Type: Article

References (15)

1. Cho J.Y., Joo H.G., Kim K.S., Zee S.Q., and Chang M.H. Three-dimensional heterogeneous whole core transport calculation employing planar MOC solution. Trans. Am. Nucl. Soc. 87 (2002) 234 Washington, District Columbia, USA, November 17-21
2. Cho J.Y., Joo H.G., Kim K.S., and Zee S.Q. Cell-based CMFD formulation for acceleration of whole-core method of characteristics calculations. J. Kor. Nucl. Soc. 35 (2002) 250
3. Cho N.Z., Lee G.S., and Park C.J. Fusion of method of characteristics and nodal method for 3-D whole-core transport calculation. Trans. Am. Nucl. Soc. 86 (2002) 322 Hollywood, Florida, USA, June 9-13
4. Finnemann H., Bennewitz F., and Wagner M.R. Interface nodal current techniques for multidimensional reactor calculations. Atomkernenergie 30 (1977) 123
5. Halsall M.J. CACTUS, A Characteristics Solution to the Neutron Transport Equations in Complicated Geometries. AEEW-R-1291 (1980), United Kingdom Atomic Energy Authority, Winfrith
6. Joo H.G., and Downar T.J. An incomplete domain decomposition preconditioning method for nonlinear nodal kinetics calculation. Nucl. Sci. Eng. 123 (1996) 403
7. Joo, H.G., Cho, J.Y., Kim, H.Y., Zee, S.Q., Chang, M.H., 2002. Dynamic implementation of the equivalence theory in the heterogeneous whole core transport calculation. In: Proc. PHYSOR2002, Paper 13A-02 on CD-ROM, Oct. 7-10, Seoul, Korea.
8. Joo, H.G., Cho, J.Y., Kim, K.S., Lee, C.C., Zee, S.Q., 2004. Methods and performance of a three-dimensional whole-core transport code DeCART. In: Proc. PHYSOR2004, CD-ROM, April 25-29, Chicago, Illinois, USA.
9. Kosaka S., and Takeda T. Verification of 3D heterogeneous core transport calculation utilizing nonlinear iteration technique. J. Nucl. Sci. Technol. 41 (2004) 645
10. Leonard A., and McDaniel C.T. Optimal polar angles and weights for the characteristics method. Trans. Am. Nucl. Soc. 73 (1995) 172
11. Lewis, E.E., Smith, M.A., Tsoulfanidis, N., Palmiotti, G., Taiwo, T.A., Blomquist, R.N., 2001. Benchmark Specification for Deterministic 2-D/3-D MOX Fuel Assembly Transport Calculations Without Spatial Homogenisation (C5G7 MOX). OECD/NEA report, NEA/NSC/DOC(2001)4.
12. Smith, K., Rhodes, III, J.D., 2002. Full-core, 2-D, LWR core calculations with CASMO-4E. In: Proc. PHYSOR2002, Paper 13A-04 on CD-ROM, Oct. 7-10, Seoul, Korea.
13. Smith, M.A., Palmiotti, G., Taiwo, T.A., Lewis, E.E., Tsoulfanidis, N., 2003. 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.
14. Smith, M.A., Lewis, E.E., Na, B.C., 2005. Benchmark on Deterministic Transport Calculation without Spatial Homogenisation: MOX Fuel Assembly 3-D extension case. OECD/NEA report, NEA/NSC/DOC (2005)16.
15. Sutton, T.M., 1989. NODEX: a high order nem-based multigroup nodal code. In: Proc. Topical Meeting on Advances in Nuclear Engineering Computation and Radiation Shielding. 38:1-3:11, April 9-13, Santa Fe, New Mexico, USA.