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FPを含むPu溶液のモニタリング技術に係る適用性調査研究,1; 概要

Feasibility study of technology for Pu solution monitoring including FP, 1; Overview

関根 恵; 鈴木 敏*; 松木 拓也; 蔦木 浩一; 谷川 聖史; 石山 港一; 中村 仁宣; 富川 裕文

Sekine, Megumi; Suzuki, Satoshi*; Matsuki, Takuya; Tsutagi, Koichi; Tanigawa, Masafumi; Ishiyama, Koichi; Nakamura, Hironobu; Tomikawa, Hirofumi

原子力機構は、再処理施設の効果的・効率的な保障措置のため、FPを含む高放射性溶液中のPuをモニタリングするための適用性調査研究を、米国エネルギー省(DOE)との共同研究として、東海再処理施設の高放射性廃液(HALW)を対象に実施している。第1段階では、簡便な方法で定性な評価が可能か確認するため、HALWの組成調査及びコンクリートセル外における放射線調査を実施した。第2段階では、セル内用放射線測定器の設計、検出器の設置位置の検討のため放射線輸送計算コードの計算モデルの最適化等に必要となるセル内の線量率を測定した。第3段階では、これまでの結果を基に設計・製作したセル内用放射線測定器を用いて測定可能な放射線を調査し、最終段階として、測定した放射線のPuモニタリングへ適用性を評価する。本発表においては、研究概要、セル外壁における放射線測定結果について報告する。

JAEA is being conducted feasibility study of technology for Pu solution monitoring including fission products (FPs) as a joint research program with U.S. DOE at the High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant to address effective and efficient safeguards for reprocessing facilities. As the first step, the design information of HALW tank was investigated and measurement test at the out of the concrete cell was conducted in order to confirm whether qualitative evaluation is possible by a simple method. As the second step, gamma dose rate was measured at the inside of the concrete cell which is necessary to optimize the MCNP model for the design and location of the detector at the inside of the concrete cell. As the third step, measureable radiations were investigated at the inside of the concrete cell by the detector which is designed and fabricated based on these outputs. As the final step measurement and simulation results will be evaluated for Feasibility study of the technology for Pu monitoring. This time, an overview and radiation measurement results at outside of cell wall will be reported.

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