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Volumn 35, Issue 2, 2008, Pages 158-166

Development and validation of a fast reactor core burnup code - FARCOB

Author keywords

[No Author keywords available]

Indexed keywords

COMBUSTION; COMPUTATIONAL GEOMETRY; COMPUTER SIMULATION; DIFFUSION; FAST REACTORS; POWER CONTROL;

EID: 37849035972     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2007.07.003     Document Type: Article
Times cited : (24)

References (22)
  • 1
    • 37849048177 scopus 로고    scopus 로고
    • Buckel, G. et al., 1985. In: National Software Centre Benchmark Problem Book, ANL-7416, Supplement-3.
  • 2
    • 33645993302 scopus 로고    scopus 로고
    • The design of prototype fast breeder reactor
    • Chetal S.C., et al. The design of prototype fast breeder reactor. Nuclear Engineering and Design 236 (2006) 852
    • (2006) Nuclear Engineering and Design , vol.236 , pp. 852
    • Chetal, S.C.1
  • 3
    • 37849036184 scopus 로고    scopus 로고
    • Derstine, K.L., 1982. DIF3D, A code to solve one-two and three dimensional diffusion finite difference diffusion theory problems, ANL-82-64.
  • 4
    • 37849003653 scopus 로고    scopus 로고
    • Devan, K. et al., 1999. Benchmark analysis with XSET-98 cross-section set, Activity Report of Reactor Physics Division-1998, IGC-210.
  • 5
    • 37849018939 scopus 로고    scopus 로고
    • Devan, K., 2003. An interface between CONSYST/ABBN-93 and IGCAR diffusion theory codes, IGCAR Report, RPD/NDS/90.
  • 6
    • 37849028530 scopus 로고    scopus 로고
    • Doriath, J.Y. et al., 1993. ERANOS, The advanced European system of codes for reactor physics calculations. In: Proc. of International Conference on Mathematical Methods and Supercomputing in Nuclear Computations, Karlsruhe, Germany.
  • 7
    • 37849031146 scopus 로고    scopus 로고
    • Fayers, F.J. et al., 1972. LWR-WIMS, A modular computer code for the evaluation of light water reactor lattices. AEEW-R-785, Part I.
  • 8
    • 37849045196 scopus 로고    scopus 로고
    • Fowler, T.B. et al., 1971. Nuclear reactor core analysis code CITATION, ORNL-TM-2496 Rev-2.
  • 9
    • 37849005288 scopus 로고    scopus 로고
    • Kim, Y.I. et al., 2002. BN-600 hybrid core benchmark analysis. In: Proc. of PHYSOR-2002, Seoul, Korea.
  • 10
    • 0025588108 scopus 로고
    • Validation of a few group 3-D core burnup calculation scheme for FBRs by analysis of critical experiments
    • Mahalakshmi B., and Mohanakrishnan P. Validation of a few group 3-D core burnup calculation scheme for FBRs by analysis of critical experiments. Annals of Nuclear Energy 17 (1990) 403-414
    • (1990) Annals of Nuclear Energy , vol.17 , pp. 403-414
    • Mahalakshmi, B.1    Mohanakrishnan, P.2
  • 11
    • 37849048474 scopus 로고    scopus 로고
    • Manturov, G.N., 1997. BNAB-93 Data Library Part I, Nuclear Data for the Calculations of Neutron and Photon Radiation Function, INDC (CCP-409), IAEA, Vienna.
  • 12
    • 37849038505 scopus 로고    scopus 로고
    • Menon, S.V.G. et al., 1981. Iterative Solutions of Finite Difference Diffusion Equations, BARC-1129.
  • 13
    • 37849016532 scopus 로고    scopus 로고
    • Mohanakrishnan, P., 1988. Development of 3-D Core Simulation Methods for Fast Reactor Cores. IGCAR report, IGC-97.
  • 14
    • 37849053907 scopus 로고    scopus 로고
    • Mohanakrishnan, P., 1992. COHINT, A Computer Code to Treat Control Rod Heterogeneity and its Application to Fast Reactor Core Analysis, IGC-130.
  • 15
    • 37849030347 scopus 로고    scopus 로고
    • Mohanakrishnan, P., Arul, J., 1998. Simulation of FBTR Core Evolution from 24 SA Core to 28 SA Core with 3D Burnup Code FARCOB, IGCAR Report, RPD/LMS/FBTR/ON/055.
  • 16
    • 37849041195 scopus 로고    scopus 로고
    • Seryogin, A.S., Kislitsyna, T.S., 1997. Abstract of TRIGEX-CONSYST-ABBN-90, IPPE-2665, Obninsk.
  • 17
    • 37849023393 scopus 로고    scopus 로고
    • Toppel, B.J., 1982. Validation of attenuation methods and date for a benchmark fast reactor depletion calculation. In: Proc. of Topical Meeting on Reactor Physics and Core Thermal Hydraulics, Kiamesha Lake.
  • 18
    • 37849020909 scopus 로고    scopus 로고
    • Toppel, B.J., 1983. The Fuel Cycle Analysis Capability REBUS-3, ANL-83-2.
  • 20
    • 37848999594 scopus 로고    scopus 로고
    • Vondy, D.R., 1977. VENTURE - A Code Block for Solving Multigroup Neutronic Problems Applying Finite Difference Diffusion Approximation to Neutron Transport, ORNL-5062R1.
  • 21
    • 37849019743 scopus 로고    scopus 로고
    • Working Material RCM-3 of IAEA-CRP on "Updated Codes and Methods to Reduce the Calculational Uncertainty of LMFR Reactivity Effects", Cadarache, Nov. 12-16, 2001, IAEA-RA-803.3, TWG-FR/106, 2001.
  • 22
    • 37849028529 scopus 로고    scopus 로고
    • Working Material RCM-1 of IAEA-CRP on Updated Codes and Methods to Reduce Calculational Uncertainties of LMFR Reactivity Effects, Vienna, Nov. 24-26, 1999, IAEA-RC-803, IWGFR/100, 2000.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.