MOX燃料データベースの開発

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Author: 生澤佳久ほか

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Publication date: 2007-03

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Note (General)：: We developed MOX Fuel Database, which included valuable data from several irradiation tests in FUGEN and Halden reactor, for help of LWR MOX use. This...

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Summary, etc.：: We developed MOX Fuel Database, which included valuable data from several irradiation tests in FUGEN and Halden reactor, for help of LWR MOX use. This...

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Material Type: 文書・図像類
Title: MOX燃料データベースの開発
Author/Editor: 生澤佳久
小澤隆之
Author Heading: 生澤佳久
小澤隆之
Publication Date: 2007-03
Publication Date (W3CDTF): 2007-03
Alternative Title: Development of MOX fuel database
Periodical title: JAEA-Technology 2007-010
Text Language Code: eng
Target Audience: 一般
Note (General): We developed MOX Fuel Database, which included valuable data from several irradiation tests in FUGEN and Halden reactor, for help of LWR MOX use. This database includes the data of fabrication and irradiation, and the results of post-irradiation examinations for seven fuel assemblies, i.e. P06, P2R, E03, E06, E07, E08 and E09, irradiated in FUGEN. The highest pellet peak burn-up reached $\sim$48 GWd/t in MOX fuels, of which the maximum plutonium content was $\sim$6 wt\%, irradiated in E09 fuel assembly without any failure. Also the data from the instrumented MOX fuels irradiated in HBWR to study the irradiation behavior of BWR MOX fuels under the steady state condition (IFA-514/565 and IFA-529), under the load-follow operation condition (IFA-554/555) and under the transit condition (IFA-591) are included in this database. The highest assembly burn-up reached $\sim$56 GWd/t in IFA-565 steady state irradiation test, and the maximum linear power of MOX fuel rods was 58.3-68.4 kW/m without any failure in IFA-591 ramp test. In addition, valuable instrument data, i.e. cladding elongation, fuel stack elongation, fuel center temperature and rod inner pressure were obtained from IFA-554/555 load-follow test.
新型転換炉原型炉ふげん及びハルデン炉(HBWR)で実施されたさまざまなMOX照射試験のデータベースを開発した。データベースには、ふげんで照射された燃料集合体(P06, P2R, E03, E06, E07, E08、及びE09)の製造データ,照射データ及び照射後試験データが含まれている。このうちE09燃料集合体はPu富化度約6wt\%で、ふげんで照射されたMOX燃料集合体で最も燃焼の進んだものでありペレットピーク燃焼度48GWd/tまで健全に照射された。一方、HBWRではBWR-MOX燃料の定常運転時の挙動評価(IFA-514/565, IFA-529),ATR-MOX燃料の日負荷追従時の挙動評価(IFA-554/555)及び過出力時の挙動評価(IFA-591)の試験が行われた。IFA-565は定常状態で照射され、最高燃焼度約56GW d/tに達している。また、IFA-591は最高線出力58.3-68.4kW/mまで破損することなく照射され、IFA-554/555では出力変動に伴う被覆管・スタック伸び,燃料中心温度,要素内圧などのデータが取得された。データベースには、これらHBWRで照射された燃料の製造データ,照射データ及び照射後試験データ及び炉内計装データも格納している。
Source: /JAEA-Technology-2007-010.pdf （fulltext）
https://jopss.jaea.go.jp/pdfdata/JAEA-Technology-2007-010.pdf
Access Restrictions: 限定公開
Data Provider (Database): 国立情報学研究所 : 学術機関リポジトリデータベース（IRDB）（機関リポジトリ）
https://irdb.nii.ac.jp
Original Data Provider (Database): 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System