大型高速炉遮蔽解析手法の開発 JASPER(日米共同高速炉遮蔽実験)実験解析の成果

庄野 彰; 角田 弘和; 竹村 守雄; 半田 博之

doi:10.3327/jaesj.38.760

大型高速炉遮蔽解析手法の開発

JASPER(日米共同高速炉遮蔽実験)実験解析の成果

庄野彰, 角田弘和, 竹村守雄, 半田博之

著者情報

ジャーナルフリー

1996 年 38 巻 9 号 p. 760-770

DOI https://doi.org/10.3327/jaesj.38.760

詳細

発行日: 1996/09/30 受付日: 1995/11/28 J-STAGE公開日: 2009/04/21 受理日: - 早期公開日: - 改訂日: -
訂正情報
訂正日: 2009/04/21 訂正理由: - 訂正箇所: 論文受付日訂正内容: 訂正後 : 19951128

訂正日: 2009/04/21 訂正理由: - 訂正箇所: 引用文献情報訂正内容: 訂正前 : (1) 大谷暢夫,他:原子力誌,25[7], 520～528 (1983).
(3) 池上哲雄,他:原子力工業,33[2], 69～79 (1987).
(4) 鈴木惣十,他:原子力工業,34[6], 48～51 (1988).
(10) 白方敬章,他:原子力学会「1987秋の大会」予稿集,A56～A61.
(18) 小山謹二,他:JAERI-M 6928, (1977).
(27) 半田博之,太田励:原子力学会「1987秋の大会」予稿集,A59, A60.
(28) Maerker, R.E., et al.: ORNL-4880, (1974). (29) 岡芳明:私信,(1987).
(29) 岡芳明:私信,(1987).
(31) 角田弘和,他:原子力学会「1989春の年会」要旨集. A4.
(32) 庄野彰,他:原子力学会「1994秋の大会」予稿集,D8～D11.
(33) 坏正義,他:同「1992秋の大会」予稿集,E36～E43.

訂正後 : (1) 大谷暢夫,他:原子力誌,25[7], 520-528 (1983).
(3) 池上哲雄,他:原子力工業,33[2], 69-79 (1987).
(4) 鈴木惣十,他:原子力工業,34[6], 48-51 (1988).
(10) 白方敬章,他:原子力学会「1987秋の大会」予稿集,A56-A61.
(18) 小山謹二,他:JAERI-M 6928, (1977).
(27) 半田博之,太田励:原子力学会「1987秋の大会」予稿集,A59, A60.
(28) Maerker, R.E., et al.: ORNL-4880, (1974). (29) 岡芳明:私信,(1987).
(29) 岡芳明:私信,(1987).
(31) 角田弘和,他:原子力学会「1989春の年会」要旨集. A4.
(32) 庄野彰,他:原子力学会「1994秋の大会」予稿集,D8-D11.
(33) 坏正義,他:同「1992秋の大会」予稿集,E36-E43.

訂正日: 2009/04/21 訂正理由: - 訂正箇所: PDFファイル訂正内容: -

抄録

All experiments planned in the JASPER, Japanese-American Shielding Program for Experimental Research, had been conducted between 1986 and 1992 under the cooperation between the U.S. Department of Energy and Power Reactor and Nuclear Fuel Development Corporation of Japan to obtain useful information on FBR shielding analysis accuracy. Tower Shielding Facility (TSF) of Oak Ridge National Laboratory was utilized for all the measurements. Results obtained from the post-experimental analyses are summarized in this report. Both characteristics for bulk shielding attenuation and streaming of neutron through configurations consisting of several materials including boron-carbide (B4C), graphite, stainless steel, sodium and etc. were clarified and the analysis accuracy confirmed. Prediction accuracy in both shielding property for configuration containing fissile material and sodium activation characteristics was confirmed. The shielding analysis system for fast reactors using a 2-dimensional discrete ordinates code as a standard has been improved and verified. Through those activities, useful information to be utilized in designing large FBR is accumulated.

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