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原子力発電所のサイト解放に関する技術的課題の検討; 米国の実績を参考としたサイト解放基準,手順,検認要件(受託研究)

Study on technical issues of site release of nuclear power plants; Criteria for site release, procedures and verification requirements based on experiences in the U.S. (Contract research)

助川 武則; 島田 太郎 ; 桂井 清道; 田中 忠夫 ; 中山 真一 

Sukegawa, Takenori; Shimada, Taro; Katsurai, Kiyomichi; Tanaka, Tadao; Nakayama, Shinichi

原子力施設の運転終了以降にかかわる安全規制制度のうち、廃止措置終了の確認に関する放射能レベルの基準,検認手法等は具体的に検討を行うべき重要な課題である。そこで、IAEA,米国等の指針や基準並びに米国発電用原子炉のサイト解放の実施例を調査し、我が国でのサイト解放の制度化について検討する場合の課題を抽出した。本報告書では、具体的事例として米国トロージャン発電所の最終放射線サーベイの手順等をまとめるとともに、広大な敷地を対象とする廃止措置終了確認における検認測定の対象範囲の設定等について考察し、さらに、米国の最終サーベイ手引き(MARSSIM)を参考に我が国における廃止措置終了確認の手順を例示した。

In the field of safety regulation systems for nuclear facilities after completion of operation, criteria of residual radioactivities and confirmation and verification procedures for termination of decommissioning are important problems that should concretely be made a study. Safety standards and criteria in IAEA, USA, etc., and practical examples of site release of power reactors in USA were studied, therefore, problems for introducing the regulation system in Japan were discussed. In this report, final status survey of Trojan power plant were investigated as a particular case of site release, and, concept of specifying survey areas to be measured radioactivities and demonstrated to compliance with release criteria was discussed. In addition, the idea of confirmation and verification procedure for termination of decommissioning in Japan was proposed referring to the US guidance (MARSSIM).

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