BN-600 HYBRID CORE BENCHMARK ANALYSES
暂无分享,去创建一个
Russian Federation | P. Mohanakrishnan | K. N. Grimm | A. Stanculescu | A. Stanculescu | P. Mohanakrishnan | Russian Federation. | R. Hill | R. N. Hill | Y. I. Kim | P. Finck | H. Song | M. Farakshin | V. Stogov | P. Finck | H. Song | V. Stogov | K. Grimm | M. Farakshin
[1] D. Ilberg,et al. Evaluated delayed neutron spectra and their importance in reactor calculations , 1977 .
[2] G. R. Keepin,et al. Physics of Nuclear Kinetics , 1967 .
[3] Taira Hazama,et al. BN-600 Hybrid Core Mock-up at BFS-2 Critical Facility , 2002 .
[4] R. D. O'Dell. Standard interface files and procedures for reactor physics codes. Version IV , 1977 .
[5] R. W. Hardie,et al. 2DB USER'S MANUAL. , 1968 .
[6] B. J. Toppel. User's guide for the REBUS-3 fuel cycle analysis capability , 1983 .
[7] K. Derstine. DIF3D: a code to solve one-, two-, and three-dimensional finite-difference diffusion theory problems. [LMFBR] , 1984 .
[8] R. S. Baker,et al. DANTSYS: A diffusion accelerated neutral particle transport code system , 1995 .
[9] H. Takano,et al. Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3 , 2002 .
[10] C. B. Carrico,et al. Variational nodal formulation for the spherical harmonics equations , 1996 .
[11] S. Kondo. SIMMER-III : An advanced computer program for LMFBR severe accident analysis , 1992 .
[12] M. C. Brady,et al. Delayed Neutron Data and Group Parameters for 43 Fissioning Systems , 1989 .
[13] J. F. Briesmeister. MCNP-A General Monte Carlo N-Particle Transport Code , 1993 .
[14] R. W. Hardie,et al. 1DX: A ONE-DIMENSIONAL DIFFUSION CODE FOR GENERATING EFFECTIVE NUCLEAR CROSS SECTIONS. , 1969 .
[15] W. Little,et al. PERT-V: A TWO-DIMENSIONAL PERTURBATION CODE FOR FAST REACTOR ANALYSIS. , 1969 .
[16] R. J. Tuttle. Delayed-neutron data for reactor-physics analysis , 1975 .
[17] R. Macfarlane,et al. LIB-IV, A Library of Group Constants for Nuclear Reactor Calculations , 1976 .