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JAEA Reports

Research and development plan for advanced high temperature gas cooled reactor fuels and graphite components (Contract research)

Sawa, Kazuhiro; Ueta, Shohei; Shibata, Taiju; Sumita, Junya; Ohashi, Jumpei; Tochio, Daisuke

JAERI-Tech 2005-024, 34 Pages, 2005/03

JAERI-Tech-2005-024.pdf:2.15MB

The Very-High-Temperature Reactor (VHTR) is one of the strong candidates for the Generation IV Nuclear Energy System. JAERI has developed Zirconium carbide (ZrC)-coated fuel particle and ZrC coating layer is expected to maintain its intactness under higher temperature and burn-up comparing conventional SiC-coating layer. JAERI carries out (1) ZrC-coating process development by large-scale coater, (2) inspection method development and (3) irradiation test and post irradiation experiment of ZrC coated particles. Also, JAERI carries out reactivity insertion tests to clarify the coating failure mechanism and tries to increase allowable temperature limit in case of reactivity insertion accident. Furthermore, JAERI develops non-destructive evaluation methods for mechanical properties of graphite components by ultrasonic testing and micro-indentation technique. This report describes these research and development plan and results of FY 2004 as a MEXT contact research.

Journal Articles

Measurement of local void fraction distribution in rod bundle under high-pressure high-temperature boil-off conditions by using optical void probe

Kumamaru, Hiroshige; Murata, Hideo; ; Kukita, Yutaka

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.217 - 222, 1995/00

no abstracts in English

JAEA Reports

HTGR fuel behavior at very high temperature

; ; ; Iwamoto, K.

JAERI-M 86-046, 17 Pages, 1986/03

JAERI-M-86-046.pdf:3.01MB

no abstracts in English

Journal Articles

Performance of the model fuel pin of the very high-temperature gas-cooled reactor at temperatures above 2000$$^{circ}$$C

;

Nucl.Eng.Des., 92, p.15 - 26, 1986/00

 Times Cited Count:6 Percentile:58.99(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Survival temperature limit of unirradiated coated fuel particles

; Ikawa, Katsuichi

JAERI-M 85-068, 19 Pages, 1985/06

JAERI-M-85-068.pdf:2.0MB

no abstracts in English

Journal Articles

HTGR fuel behavior at very high temperature

; ; Iwamoto, K.

Transactions of the American Nuclear Society, 50, p.241 - 242, 1985/00

no abstracts in English

JAEA Reports

Reactor Engineering Division Annual Report; April 1, 1978-March 31, 1979

Hirota, Jitsuya

JAERI-M 8393, 166 Pages, 1979/09

JAERI-M-8393.pdf:4.79MB

no abstracts in English

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