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JAEA Reports

Solutions to NEANSC benchmark problems on Power Distribution within Assemblies(PDWA) using the SRAC and GMVP

Kugo, Teruhiko; Nakakawa, Masayuki;

JAERI-M 92-117, 70 Pages, 1992/08

JAERI-M-92-117.pdf:1.39MB

no abstracts in English

JAEA Reports

Development of a ThreeDimensional Neutron Diffusion Code Series by Leakage Iterative Method

JAERI-M 8238, 29 Pages, 1979/05

JAERI-M-8238.pdf:0.61MB

no abstracts in English

JAEA Reports

FEMRZ:Program for solving two-dimensional neutron transport problems in cylindrical geometry by the finite element method

; ; ; *;

JAERI 1253, 29 Pages, 1978/02

JAERI-1253.pdf:1.22MB

no abstracts in English

Journal Articles

Application of finite element method to two-dimensional multi-group neutron transport equation in cylindrical geometry

; ; ; ; *

Journal of Nuclear Science and Technology, 14(8), p.541 - 550, 1977/08

https://doi.org/10.3327/jnst.14.541
 Times Cited Count：3

no abstracts in English

Journal Articles

Application of coarse-mesh rebalance acceleration to Monte Carlo eigenvalue problems

; ; ; ; ; ; ;

Nuclear Science and Engineering, 59(4), p.326 - 336, 1976/04

https://doi.org/10.13182/NSE76-A26835
 Times Cited Count：3

no abstracts in English

JAEA Reports

Modification of the MORSE code for Monte Carlo eigenvalue problems by coarse-meth rebalance acceleration

; ; ; ; ;

JAERI-M 6251, 36 Pages, 1975/09

JAERI-M-6251.pdf:0.87MB

no abstracts in English

JAEA Reports

The Evaluation of Method How to Calculate Three-Dimensional Power Distribution and the Development of the Code FLORA

JAERI-M 6232, 103 Pages, 1975/09

JAERI-M-6232.pdf:2.78MB

no abstracts in English

JAEA Reports

Convergence Acceleration Algorithms of Iterative Methods used in Nuclear Reactor Analysis Codes

;

JAERI-M 5590, 48 Pages, 1974/03

JAERI-M-5590.pdf:1.39MB

no abstracts in English

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