Verification of 3d heterogeneous core transport calculation utilizing non-linear iteration technique

Journal of Nuclear Science and Technology

Volumn 41, Issue 6, 2004, Pages 645-654

  Kosaka, Shinya ^a   Takeda, Toshikazu ^b  

^a TEPCO SYSTEMS CORPORATION   (Japan)

^b OSAKA UNIVERSITY   (Japan)

Author keywords

CHAPLET 3D; Deterministic method; Heterogeneous 3D core analysis; Method of characteristics; Non linear iteration technique

Indexed keywords

CHAPLET-3D; DETERMINISTIC METHODS; HETEROGENEOUS 3D CORE ANALYSIS; METHOD OF CHARACTERISTICS; NONLINEAR ITERATION TECHNIQUES;

CODES (STANDARDS); COMPUTATIONAL METHODS; CORE ANALYSIS; DIFFUSION; ITERATIVE METHODS; MONTE CARLO METHODS; NONLINEAR SYSTEMS; NUCLEAR ENGINEERING;

REACTOR CORES;

EID: 4043141583     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2004.9715529     Document Type: Article

References (13)

1. S. Kosaka, E. Saji, “Transport theory calculation for a heterogeneous multi-assembly problem by characteristics method with direct neutron path linking technique,” J. Nucl. Sci. Technol., 37[12], 1015 (2000).
2. N. Z. Cho, et al., “Whole-core heterogeneous transport calculations and their comparisons with diffusion Results,” Trans. Am. Nucl. Soc., 83, 292 (2000).
3. K. S. Smith, J. D. Rhodes, “CASMO-4 characteristics method for two-dimensional PWR and BWR core calculations,” Trans. Am. Nucl. Soc., 83, 294 (2000).
4. N. Z. Cho, et al., “Fusion of method of characteristics and nodal method for 3-D whole-core transport calculation,” Trans. Am. Nucl. Soc., 86, 322 (2002).
5. H. G. Joo, et al., “Dynamic implementation of the equivalence theory in the heterogeneous whole core transport calculation,” Proc. Int. Conf. On the New Front. Of Nucl. Technol. Reac. Phys., Safety and High-Perform. Comp., Seoul, Korea, Oct. 7-10, 2002, on CD-ROM, (2002).
6. S. Kosaka, T. Takeda, “Diffusion-like 3-D heterogeneous core calculation with 2-D characteristics transport correction by non-linear iteration technique,” Proc. Int. Conf. Nucl. Math. and Comp. Sci., Gatlinburg, U.S.A., Apr. 6-11 2003, on CD-ROM, (2003).
7. J. Y. Cho, et al., “Three-dimensional heterogeneous whole core transport calculation employing planar MOC solutions,” Trans. Am. Nucl. Soc., 87, 234 (2002).
8. K. S. Smith, “Nodal method storage reduction by nonlinear iteration,” Trans. Am. Nucl. Soc., 44, 265 (1984).
9. C. Lee, T. J. Downar, “Nonlinear formulation for multigroup simplified P3,” Trans. Am. Nucl. Soc., 83, 297 (2000).
10. H. Finnemann, et al., “Interface current techniques for multidimensional reactor calculations,” Atomkernernergie, 30, 123 (1977).
11. D. G. Knott, M. Edenius, “Validation of the CASMO-4 transport solution,” Proc. Math. Methods and Supercomputing in Nuclear Application, Karlsruhe, Germany, Vol. 2, 547 (1993).
12. T. Mori, M. Nakagawa, JAERI-Data/Code 94-007, (1994).
13. M. J. Halsall, CACTUS, A Characteristics Solution to the Neutron Transport Equations in Complicated Geometries, AEEW-R1291, UKAEA, Winfrith, (1980).