BEHAVIORS OF MOLYBDENUM IN UO2 FUEL MATRIX

被引：10

作者：

Ha, Yeong-Keong ^{[1
]}

Kim, Jong-Goo ^{[1
]}

Park, Yang Soon ^{[1
]}

Park, Soon Dal ^{[1
]}

Song, Kyuseok ^{[1
]}

机构：

[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2011年 / 43卷 / 03期

关键词：

Molybdenum; Uranium Dioxide; Distribution; Chemical State; Oxidation; FISSION-PRODUCTS; CHEMICAL-STATE; PHASES;

D O I：

10.5516/NET.2011.43.3.309

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Molybdenum is the most abundant fission product since its fission yield is equivalent to that of xenon, and it has a very special role in the chemistry of nuclear fuel because it influences the oxygen potential of UO2 fuel. In this study, the distribution of molybdenum in spent UO2 fuel specimens with 33.3, 41.0 and 57.6 GWd/tU burnup was measured by a LA-ICP-MS system and the reproducibility of the measured data was obtained. The Mo distribution was almost constant along the radius of a fuel except an increase at the periphery of the fuel. It showed a drop in reproducibility with relatively high deviation of measured values for the highest burnup fuel. To explain this, the state of molybdenum in a UO2 matrix and its effect on the oxidation behavior of UO2 were investigated. The low reproducibility was explained by the segregation of molybdenum, and the inhibition of oxidation by the molybdenum was also observed.

引用

页码：309 / 316

页数：8

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