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Naito, Yoshitaka

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Development of a three-dimensional neutron diffusion code series by leakage iterative method
1979
Naito Yoshitaka
2078
0
OECD/NEA burnup credit criticality benchmarks phase IIIB: burnup calculations of BWR fuel assemblies for storage and transport = Расчет критичности отработавших топливных сборок при хранении и транспортировке
2002
Okuno Hiroshi, Naito Yoshitaka, Suyama Kenya
2110
0
Data book of the isotopic composition of spent fuel in light water reactors
1994
Naito Yoshitaka, Kurosawa Masayoshi, Kaneko Toshiyuki
1418
0
DATA-POOL : A direct-access data base for large-scale nuclear codes
1991
Yamano Naoki, Koyama Kinij, Naito Yoshitaka, Minami Kazuyoshi
2929
0
Steady-ACE : A computer program for three-dimensional nuclear a. thermal-hydraulic analysis of BWR core
1980
Naito Yoshitaka, Abe Kiyoharu, Maekawa Mitsuru
711
0
A three-dimensional neutron diffusion calculation code : Diffusion-ACE
1979
Naito Yoshitaka, Maekawa Mitsuru, Shibuya Kazuo
2508
0
OECD/NEA burnup credit criticality benchmarks phase IIIA : Criticality calculations of BWR spent fuel assemblies in storage a. transport = Расчет критичности отработавших топливных сборок при хранении и транспортировке.
2000
Okuno Hiroshi, Naito Yoshitaka, Ando Yoshihira
987
0
MKENO-DAR : A direct angular representation Monte Carlo code for criticality safety analysis
1984
Naito Yoshitaka
629
0
User's manual of the MKENO-DAR code system
1986
Naito Yoshitaka, Nakae Hirochika
2510
0
A general dimensional neutron diffusion calculation code : ADC
1979
Akimoto Masayuki, Naito Yoshitaka
1484
0
MUTUAL : A computer code for analysing nuclear criticality safety on array system
1986
Naito Yoshitaka, Naneko Toshiyuki, Okuno Hiroshi
2813
0
Data for the core identification of research and test reactors at JAERI
1980
Naito Yoshitaka, Kachi Kunio, Kurosawa Masayoshi, Naito Yoshitaka, Kachi Kunio, Kurosawa Masayoshi
871
0