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JAEA Reports

Study on disposal method of graphite blocks and storage of spent fuel for modular gas-cooled reactor (Joint research)

Sumita, Junya; Sawa, Kazuhiro; Tsuchie, Yasuo*; Urakami, Masao*; Kunitomi, Kazuhiko

JAERI-Tech 2002-104, 23 Pages, 2003/02

JAERI-Tech-2002-104.pdf:1.15MB

This report describes the result of study on disposal method of graphite blocks in future block-type reactor. Present study was carried out within a framework of joint research, "Research of Modular High Temperature Gas-cooled Reactors (No. 3)", between Japan Atomic Energy Research Institute (JAERI) and the Japan Atomic Power Company (JAPCO), in 2000. In this study, activities in fuel and reflector graphite blocks were evaluated and were compared with the disposal limits defined as low-level of radioactive waste. As a result, it was found that the activity for only C-14 was higher than disposal limits for the low-level of radioactive waste and that the amount of air in the graphite is important to evaluate precisely of C-14 activity. In addition, spent fuels can be stored in air-cooled condition at least after two years cooling in the storage pool.

JAEA Reports

User's manual for seismic analysis code "SONATINA-2V"

Hanawa, Satoshi; Iyoku, Tatsuo

JAERI-Data/Code 2001-021, 150 Pages, 2001/08

JAERI-Data-Code-2001-021.pdf:6.16MB

no abstracts in English

Journal Articles

Coupling effect of core-bottom structure and core graphite blocks in HTTR

Iyoku, Tatsuo; Futakawa, Masatoshi; Shirai, Hiroshi*; Shiozawa, Shusaku; Ishihara, Masahiro; Takikawa, Noboru*

Proc. of the 12th Int. Conf. on Structural Mechanics in Reactor Technology,Vol. K; SMiRT 12, p.97 - 102, 1993/00

no abstracts in English

Journal Articles

Experimental studies on thermal and hydraulic performance of fuel stack of VHTR, VI; Results of crossflow test by HENDEL multi-channel test rig

Takase, Kazuyuki; Hino, Ryutaro;

Nihon Genshiryoku Gakkai-Shi, 33(6), p.564 - 573, 1991/06

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Thermal Stress Analysis on the Graphite Block of the Fuel Element for OGL-1 Irradiation

Minato, Kazuo; ; ; Ikawa, Katsuichi

JAERI-M 83-167, 24 Pages, 1983/10

JAERI-M-83-167.pdf:0.81MB

no abstracts in English

JAEA Reports

Analysis of Bowing of Irradiated OGL-1 Fuel Rod

Minato, Kazuo; ; ; ; Ikawa, Katsuichi; Iwamoto, K.; ; ;

JAERI-M 83-055, 77 Pages, 1983/03

JAERI-M-83-055.pdf:3.0MB

no abstracts in English

Journal Articles

Simplified analytical model for HTGR core seismic response

; *

Journal of Nuclear Science and Technology, 16(8), p.605 - 612, 1979/00

 Times Cited Count:2

no abstracts in English

Journal Articles

A Seismic analysis method for a block column gas-cooled reactor core

; *

Nucl.Eng.Des., 55(3), p.331 - 342, 1979/00

 Times Cited Count:16

no abstracts in English

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