Author Search Results

1

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Critical and subcritical masses of Curium-245, -246 and -247 calculated with a combination of MCNP4A code and JENDL-3.2 library Hiroshi Okuno, Hiromitsu Kawasaki.

by Okuno, Hiroshi
Published 2000

2

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OECD/NEA burnup credit criticality benchmarks phase IIIA : criticality calculations of BWR spent fuel assemblies in storage and transport Hiroshi Okuno, Yoshitaka Naito, Yoshihira...

by Okuno, Hiroshi
Published 2000

3

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OECD/NEA burnup credit criticality benchmarks phase IIIB : burnup calculations of BWR fuel assemblies for storage and transport Hiroshi Okuno, Yoshitaka Naito, Kenya Suyama.

by Okuno, Hiroshi
Published 2002

4

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OECD/NEA burnup credit criticality benchmark : results of phase II A Makoto Takano, Hiroshi Okuno.

by Takano, Makoto
Published 1996

Other Authors: '; “...Okuno, Hiroshi...”

5

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Nuclear criticality safety handbook (English translation) Compiled by Nuclear materials regulation division/ Nuclear safety bureau/ Science and technology agency; Translated by Yos...

Published 1995

Other Authors: '; “...Okuno, Hiroshi...”

6

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Development of a new simulation code for evaluation of criticality transients involving fissile solution boiling Benan Basoglu ... [et al.].

by Basoglu, Benan
Published 1998

Other Authors: '; “...Okuno, Hiroshi...”

7

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Extended calculations of OECD/NEA phase II-C burnup credit criticality benchmark problem for PWR spent fuel transport cask by using MCNP-4B2 code and JENDL-3.2 library Takeshi Kuro...

by Kuroishi, Takeshi
Published 2003

Other Authors: '; “...Okuno, Hiroshi...”

8

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Analyses of PWR spent fuel composition using scale and swat code system to find correction factors for criticality safety applications adopting burnup credit Hee Sung Shin ... [et...

by Shin, Hee Sung
Published 2001

Other Authors: '; “...Okuno, Hiroshi...”