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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.

JAEA Reports

Thermal hydraulic analysis of the JMTR improved LEU-core

Tabata, Toshio; Nagao, Yoshiharu; Komukai, Bunsaku; Naka, Michihiro; Takeda, Takashi*; Fujiki, Kazuo

JAERI-Tech 2002-100, 108 Pages, 2003/01

JAERI-Tech-2002-100.pdf:4.44MB

After the investigation of the new core arrangement for the JMTR reactor in order to enhance the fuel burn-up and consequently extend the operation period, the "improved LEU core" that utilized 2 additional fuel elements instead of formerly installed reflector elements, was adopted. This report describes the results of the thermal-hydraulic analysis of the improved LEU core as a part of safety analysis for the licensing. The analysis covers steady state, abnormal operational transients and accidents, which were described in the annexes of the licensing documents as design bases events. Calculation conditions for the computer codes were conservatively determined based on the neutronic analysis results and others. The results of the analysis, that revealed the safety criteria were satisfied on the fuel temperature, DNBR and primary coolant temperature, were used in the licensing. The operation license of the JMTR with the improved LEU core was granted in March 2001, and the reactor operation with new core started in November 2001 as 142nd operation cycle.

Journal Articles

Effect of 120 MeV oxygen ion irradiation on current-voltage characteristics in YBaCuO

Iwase, Akihiro; ; Iwata, Tadao; Nihira, Takeshi*

Mat. Res. Soc. Symp. Proc., Vol. 209, p.847 - 851, 1991/00

no abstracts in English

Journal Articles

Effect of high-energy ion irradiation on current-voltage characteristics in the oxide superconductor YBa$$_{2}$$Cu$$_{3}$$O$$_{7-x}$$

Iwase, Akihiro; ; Iwata, Tadao; Nihira, Takeshi*

Japanese Journal of Applied Physics, 29(10), p.L1810 - L1812, 1990/10

 Times Cited Count:3 Percentile:23.96(Physics, Applied)

no abstracts in English

JAEA Reports

JAEA Reports

Study for Thermal Problems in ORNL-Large Coil Task

;

JAERI-M 7546, 37 Pages, 1978/02

JAERI-M-7546.pdf:0.92MB

no abstracts in English

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