Preliminary test results for post irradiation examination on the HTTR fuel

Ueta, Shohei   ; Umeda, Masayuki; Sawa, Kazuhiro; Sozawa, Shizuo; Shimizu, Michio; Ishigaki, Yoshinobu; Obata, Hiroyuki*

The future post-irradiation program for the first-loading fuel of the HTTR is scheduled using the HTTR fuel handling facilities and the Hot Laboratory in the Japan Materials Testing Reactor (JMTR) to confirm its irradiation performance and to obtain data on its irradiation characteristics in the core. This report describes the result of preliminary test and the future plan for post-irradiation examination for the HTTR fuel. In the preliminary test, dimension measurement, weight measurement, fuel failure fraction measurement, burnup measurement, X-ray radiograph, SEM and EPMA observations have been carried out. Finally, it was confirmed that the first-loading fuel of the HTTR showed good quality under irradiation condition.