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

页码：1085 / 1096

页数：12

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