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Radiation detection and measurement in patients contaminated with alpha emitters

$$alpha$$核種の体内汚染の測定について

百瀬 琢麿 ; 栗原 治; 高田 千恵 ; 古田 定昭

Momose, Takumaro; Kurihara, Osamu; Takada, Chie; Furuta, Sadaaki

核燃料取扱施設等で扱われているプルトニウム等の人工放射性核種の放射線管理方法について紹介する。再処理施設で行われている放射能除染方法,汚染管理のためのさまざまな測定方法及び内部被ばくを検知するモニタリング方法について述べる。その中でも特に、オートラジオグラフィを利用したスミヤ試料の$$alpha$$核種の測定方法や鼻スミヤのサンプリング及び測定方法及び$$alpha$$核種の体内及び体外測定について紹介する。また、$$alpha$$核種の吸入事故の際の被ばく量推定のための計算コードについても紹介する。

The basic principle of radiation control at plutonium facility such as characteristics of plutonium and relevant radionuclide which are operated in nuclear fuel cycle facilities is introduced and potential radioactive contaminations in accident is discussed. As a practice, decontamination procedure of skin at Tokai Reprocessing Plant, some of the operating principles and applications of various radiation detection and measurement instruments for contamination control and occupational monitoring for internal contamination are introduced. Special methods of measurement for alpha emitters for performing radiological monitoring such as radio autography of plutonium contamination on smear samples, nasal swab sampling and measurement, in vivo and in vitro analysis for plutonium and uranium have been improved and proven. The internal dose calculation code was originally developed in order to estimate retrospectively in case of accidental intake of plutonium.

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