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JAEA Reports

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.

Journal Articles

Nuclear, thermal and hydraulic design for Gas Turbine High Temperature Reactor (GTHTR300)

Nakata, Tetsuo*; Katanishi, Shoji; Takada, Shoji; Yan, X.; Kunitomi, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.478 - 489, 2003/12

no abstracts in English

Journal Articles

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

Journal Articles

Laminar mixed convection with flow reversal in a horizontal isothermal square channel

Kunugi, Tomoaki; *; *

Therm. Sci. Eng., 2(3), p.9 - 17, 1994/00

no abstracts in English

Journal Articles

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

 Times Cited Count:0 Percentile:0.32(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal and hydraulic tests of test sections in helium engineering demonstration loop

; Suzuki, Kunihiro; Hino, Ryutaro; Takase, Kazuyuki; Inagaki, Yoshiyuki; Ioka, Ikuo

Nucl. Eng. Des., 120, p.435 - 445, 1990/00

 Times Cited Count:3 Percentile:40.88(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

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

; ; *; *; *; *; *; *

JAERI-M 85-182, 304 Pages, 1985/11

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

no abstracts in English

Journal Articles

Thermal performance test of the hot gas ducts of HENDEL

; ; ; Sanokawa, Konomo

Nucl.Eng.Des., 83, p.91 - 103, 1984/00

 Times Cited Count:4 Percentile:45.9(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

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

; ; ; ; ; ; ; ; ; ; et al.

JAERI-M 6895, 170 Pages, 1976/12

JAERI-M-6895.pdf:5.49MB

no abstracts in English

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