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- Material Type
- 規格・テクニカルリポート類
- Author/Editor
- 田代 信介阿部 仁
- Publication Date
- 2016-03
- Publication Date (W3CDTF)
- 2016
- Alternative Title
- Study on release behavior of radioiodine from fuel solution under criticality accident condition
- Periodical title
- JAEA-Technology 2015-044
- Target Audience
- 一般
- Note (General)
- 出版タイプ： NA再処理施設における溶液燃料臨界事故時の放射性ヨウ素の気相への移行挙動を把握することは、同事故における公衆への影響を評価する観点から極めて重要である。本報では、過渡臨界実験装置(TRACY)を用いた臨界実験において、臨界を終息させた後、溶液燃料中の放射性ヨウ素濃度が減少傾向を示す時間まで溶液燃料を保持した条件及び臨界を継続させた状態で溶液燃料を保持した条件の下で、TRACY炉心気相に移行した$^{133}$Iの経時的な放射能濃度を測定した。得られた経時的な炉心タンク気相中の放射性ヨウ素濃度測定値に、放射性ヨウ素の移行評価モデルを適用することで、放射性ヨウ素の気相への積算移行割合及び移行速度を評価した。過渡臨界後に臨界を終息させ溶液燃料を炉心タンク内に保持した場合には、$^{133}$Iの気相への移行速度は、ほぼ1時間後から3時間後までの時間帯で最大値を示し、8時間以降でほぼ一定となることが分かった。また、経過時刻毎の全核分裂数と移行速度の関係を得ることができた。一方、JCO臨界事故のように臨界が継続した状態で溶液燃料を保持した場合には、放射性ヨウ素の積算移行割合と移行速度は時間とともに単調に増加することが分かった。In order to estimate public dose under a criticality accident in fuel solution of a fuel reprocessing plant, release behavior of radioiodine from the fuel solution to atmosphere is very important. In this report, time evolution of $^{133}$I concentration in gas phase of TRACY core tank was measured until the concentration in the solution decreased. Furthermore, cumulative release ratio (CRR) and release rate (RR) from the solution to the atmosphere of radioiodine were evaluated by applying previously-reported evaluation model. As a result, for the case of short transient criticality, RR of $^{133}$I became maximum at 1 hour later from the ending and almost constant after 8 hour later. Furthermore, relationship of each elapsed time between total fission number and release rate of $^{133}$I could be derived. On the other hand, for the case of long criticality excursion, such as JCO criticality accident, the CRR and RR of radioiodine increased monotonously with time.
- Source
- /JAEA-Technology-2015-044.pdf （fulltext）