Re-evaluation of nuclear criticality characteristics for infinite and finite heterogeneous lattice systems composed of uranium-zirconium hydride fuel rods used in the TRIGA annular core pulse reactor NSRR

Yanagisawa, Hiroshi; Motome, Yuiko

JAEA-Research 2025-010, 197 Pages, 2025/11

JAEA-Research-2025-010.pdf:3.5MB

For understandings of nuclear criticality risks of TRIGA fuel rods and review of safety measures for handling them, nuclear criticality characteristics for infinite and finite heterogeneous lattice systems composed of the NSRR fuel rods were re-evaluated with the use of a detailed computational model for the fuel rod. The MVP version 3 code was used with the JENDL libraries including the latest version, JENDL-5, for the re-evaluation. As the criticality characteristics, variations of neutron multiplication factors of the infinite and water-reflected finite systems were examined in detail with parameters of the lattice pitch and density of moderator water. From the results of the re-evaluated criticality characteristics, the minimum critical number of fuel rods for the water-reflected hexagonal shaped lattice system was obtained to be 46.8 0.2 using the JENDL-5 library. Moreover, the attainability of criticality without the water as moderator and reflector was examined because the zirconium hydride moderator and graphite reflector are equipped with the TRIGA fuel rod. It was found that the criticality is possible to be attained by 115.7 0.6 of the number of fuel rods, which is the smaller number of fuel rods than loaded in the NSRR standard core, even though no water exists.

Performance evaluations of a high conversion boiling water reactor core with an axially heterogeneous core concept

; Okumura, Keisuke;

JAERI-M 92-067, 35 Pages, 1992/05

JAERI-M-92-067.pdf:1.06MB

no abstracts in English

Experimental Study of Large Scale Axially Heterogeneous LMFBR Core at FCA(V) ; Experiments of FCA Assembly XII-2 and their Analysis

; ; ; ; ;

JAERI-M 86-016, 51 Pages, 1986/02

JAERI-M-86-016.pdf:1.2MB

no abstracts in English

Thermal neutron spectrum in a heterogeneous reactor

Nuclear Science and Engineering, 5, P. 338, 1959/00

no abstracts in English