- 著者
-
佃 由晃
林 洋
上村 勝一郎
服部 年逸
金子 浩久
師岡 慎一
光武 徹
秋葉 美幸
安部 信明
藁科 正彦
増原 康博
木村 次郎
田辺 朗
西野 祐治
井坂 浩順
鈴木 理一郎
- 出版者
- Atomic Energy Society of Japan
- 雑誌
- 日本原子力学会和文論文誌 (ISSN:13472879)
- 巻号頁・発行日
- vol.1, no.4, pp.384-403, 2002
- 被引用文献数
-
5
Nuclear Power Engineering Corporation (NUPEC) has conducted a proving test for thermal-hydraulic performance of BWR fuel (high-burnup 8×8, 9×9) assemblies entrusted by the Ministry of Economy, Trade and Industry (NUPECTH-B Project). The high-burnup 8×8 fuel (average fuel assembly discharge burnup: about 39.5GWd/t), has been utilized from 1991. And the 9×9 fuel (average fuel assembly discharge burnup: about 45GWd/t), has started to be used since 1999. There are two types (A-type and B-type) of fuel design in 9×9 fuel assembly.<BR>Using an electrically heated test assembly which simulated a BWR fuel bundle on full scale, flow induced vibration, pressure drop, critical power under steady state condition and post-boiling transition (post-BT) tests were carried out in an out-of pile test facility that can simulate the high pressure and high temperature conditions of BWRs. This paper completed the results of 9×9 fuel combined with the previously reported results of high-burnup 8×8 fuel.<BR>As a result of NUPEC-TH-B Project, the validity of the current BWR thermal-hydraulic design method was confirmed and the reliability of BWR thermo-hydraulic fuel performance was demonstrated. Based on the test data, a new correlation of the estimation of fuel rod vibration amplitude, new post-BT heat transfer and rewet correlations for the estimation of fuel rod surface temperature were developed.