TRIGA fuel enrichment verification based on the measurement of short-lived fission products

被引：5
作者：
Peir, JJ
Wang, TK [1 ]
Liu, CC
机构：
[1] Natl Tsing Hua Univ, Dept Engn & Syst Sci, Hsinchu 30043, Taiwan
[2] Natl Tsing Hua Univ, Nucl Sci & Technol Dev Ctr, Hsinchu 30043, Taiwan
来源：
APPLIED RADIATION AND ISOTOPES | 1999年 / 50卷 / 06期
关键词：
D O I：
10.1016/S0969-8043(98)00131-6
中图分类号：
O61 [无机化学];
学科分类号：
070301 ; 081704 ;
摘要：
A method is developed to verify the U-235 content of TRIGA fresh fuel using gamma-ray spectrometry of the short-lived fission products Zr-97/Nb-97, I-132 and La-140. The short-lived fission-product activities can be established by irradiating the fuel in a nuclear reactor. Based on the measured activities, the U-235 content can be deduced by iterative calculations. The aim of this work is to establish a calibration method for estimating the burnup values of the rod-type spent fuels without the need for detailed data on fuel irradiation history. (C) 1999 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码：1085 / 1096
页数：12
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