Methods and performance of a three-dimensional whole-core transport code DeCART

Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

Volumn , Issue , 2004, Pages 21-34

  Joo, Han Gyu ^a   Cho, Jin Young ^a   Kim, Kang Seog ^a   Lee, Chung Chan ^a   Zee, Sung Quun ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

2D 1D Coupling; CMFD; MOC; Subgroup Method; Subpin Level Thermal Feedback; Whole Core Transport

Indexed keywords

APPROXIMATION THEORY; CODES (STANDARDS); DIFFUSION; FINITE DIFFERENCE METHOD; ISOTOPES; NEUTRONS; PARALLEL ALGORITHMS; PROBLEM SOLVING; THERMAL EFFECTS;

2D-1D COUPLING; CMFD; MOC; SUBGROUP METHODS; SUBPIN LEVEL THERMAL FEEDBACK; WHOLE-CORE TRANSPORT;

NUCLEAR ENERGY;

EID: 22344449157     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (16)

1. M. J. Halsall, "CACTUS, A Characteristics Solution to the Neutron Transport Equations in Complicated Geometries," AEEW-R-1291, United Kingdom Atomic Energy Authority, Winfrith (1980).
2. H. G. Joo, et al., "Dynamic Implementation of the Equivalence Theory in the Heterogeneous Whole Core Transport Calculation," PHYSOR2002, Oct. 7-10, 2002, Seoul, Korea, Paper 13A-02, CD-ROM (2002).
3. K. Smith and J. D. Rhodes, III, "Full-Core, 2-D, LWR Core Calculations with CASMO-4E," PHYSOR2002, Oct. 7-10, 2002, Seoul, Korea, Paper 13A-04, CD-ROM (2002).
4. H. Finnemann, et al., "Interface Nodal Current Techniques for Multidimensional Reactor Calculations," Atomkeraenergie, 30, 123 (1977).
5. R. J. J. Stamm'ler, "HELIOS Methods," Studsvik Scanpower (2002).
6. OECD/NEA, "Benchmark on Deterministic Transport Calculation with Spatial Homogenization," OECD/NEA Report, NEA/NSC/DOC(2003)16, (2003).
7. B. C. Na, "Benchmark on the Three-Dimensional VENUS-2 MOX Core Measurements," OECD/NEA Report, NEA/NSC/DOC (2003).
8. Z. Zhong, T. J. Downar, H. G. Joo, and J. Y. Cho, "Benchmark Analysis of the DeCART MOC Code with the VENUS-2 Critical Experiment," Proc. PHYSOR2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, Illinois, April 25-29, CD-ROM, American Nuclear Society, Lagrange Park, IL. (2004).
9. H. J. Shim, B. S. Han, and C. H. Kim, "Numerical Experiment on Variance Biases and Monte Carlo Neutronics Analysis with Thermal Hydraulic Feedback," International Conference on Supercomputing in Nuclear Application, SNA03, Paris, France, Sept. 22-24, 2003, Paper 103, CD-ROM (2003).
10. H. G. Joo, et al., "Consistent Comparison of Monte Carlo and Whole-Core Transport Solutions for Cores with Thermal Feedback," Proc. PHYSOR2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, Illinois, April 25-29, on CD-ROM, American Nuclear Society, Lagrange Park, IL. (2004).
11. H. G. Joo, et al., "Effectiveness of the Whole Core Transport Calculation with Pin-Wise Thermal Feedback" Advances in Nuclear Fuel Management III (ANFM 2003) Hilton Head Island, South Carolina, USA, October 5-8, 2003, CD-ROM, American Nuclear Society, LaGrange Park, IL (2003).
12. B. O. Cho et al., "MASTER-2.0: Multi-purpose Analyzer for Static and Transient Effects of Reactors," KAERI/TR-1211/99, Korea Atomic Energy Research Institute, Jan. 1999 (1999).
13. J. Y. Cho, at al., "Parallelization of Three-Dimensional Whole Core Transport Code DeCART," International Conference on Supercomputing in Nuclear Application, SNA03, Paris, France, Sept. 22-24, 2003, Paper 62, CD-ROM (2003).
14. J. Y. Cho, H. G. Joo, K. S. Kim, and S. Q. Zee, "Cell-Based CMFD Formulation for Acceleration of Whole-core Method of Characteristics Calculations," J. Kor Nucl Soc., 35, pp. 250-258 (2002).
15. J. Y. Cho, et al., "Three-Dimensional Whole Core Transport Calculation Methodology of the DeCART Code," KAERI Report TR-2365/2003 (2003).
16. H. G. Joo and T. J. Downar. "An Incomplete Domain Decomposition Preconditioning Method for Nonlinear Nodal Kinetics Calculation," Nucl. Sci. Eng., 123, pp.403-414 (1996).