Validation of the TAC/BLOOST code (Contract research)

Takamatsu, Kuniyoshi; Nakagawa, Shigeaki

JAERI-Data/Code 2005-003, 31 Pages, 2005/06

JAERI-Data-Code-2005-003.pdf:4.83MB

Safety demonstration tests using the High Temperature engineering Test Reactor (HTTR) are in progress to verify the inherent safety features for High Temperature Gas-cooled Reactors (HTGRs). The coolant flow reduction test by tripping gas circulators is one of the safety demonstration tests. The reactor power safely brings to a stable level without a reactor scram and the temperature transient of the reactor-core is very slow. The TAC/BLOOST code was developed to analyze reactor and temperature transient during the coolant flow reduction test taking account of reactor dynamics. This paper describes the validation result of the TAC/BLOOST code with the measured values of gas circulators tripping tests at 30 % (9 MW). It was confirmed that the TAC/BLOOST code was able to analyze the reactor transient during the test.

Comparison of JRR-4 core neutronic performance between silicide fuel and TRIGA fuel

Nakano, Yoshihiro; Ichikawa, Hiroki; Nakajima, Teruo

Proc. of the 16th Int. Meeting on Reduced Enrichment for Research and Test Reactors, 0, p.313 - 320, 1994/03

no abstracts in English

Thermal performance test of coaxial double tube hot gas duct

Ioka, Ikuo; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Shimomura, Hiroaki

Nihon Genshiryoku Gakkai-Shi, 32(12), p.1221 - 1223, 1990/12

https://doi.org/10.3327/jaesj.32.1221

no abstracts in English

Status and Future Studies of the IHX Design of the ex.VHTR

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JAERI-M 85-182, 304 Pages, 1985/11

JAERI-M-85-182.pdf:9.26MB

no abstracts in English

Reference Core Design Mark-III for Experimental Multi-Purpose VHTR

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JAERI-M 6895, 170 Pages, 1976/12

JAERI-M-6895.pdf:5.49MB

no abstracts in English