Transport criticality analysis of FBR MONJU initial critical core in whole core simulation by NSHEX and GMVP

Ishibashi, Junichi; Nishi, Hiroshi

This work presents new results obtained by the 3D hexagonal transport nodal code nshex, first time applied for monju criticality analysis in whole core simulation and up to 70 energy groups. On the grounds of the presented applied results, the method of evaluation of energy-group dependent transport correction can be recommended instead of the conventional method assuming inter-independency of energy group approximation and transport effect.

Language	:	English
Journal	:	Journal of Nuclear Science and Technology
Volume	:	41
Number	:	4
Pages	:	p.493 - 501
Publication Year/Month	:	2004/04
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Paper URL	:	https://doi.org/10.3327/jnst.41.493
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Registration No. : 04-2003-0033
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