Extension of the TRANSURANUS plutonium redistribution model for fast reactor performance analysis

被引：19

作者：

Di Marcello, Valentino ^{[1
]}

Schubert, Arndt ^{[1
]}

van de Laar, Jacques ^{[1
]}

Van Uffelen, Paul ^{[1
]}

机构：

[1] European Commiss, Joint Res Ctr, Inst Transuranium Elements, D-76344 Eggenstein Leopoldshafen, Germany

来源：

NUCLEAR ENGINEERING AND DESIGN | 2012年 / 248卷

关键词：

ACTINIDE REDISTRIBUTION; VAPOR MIGRATION; FUEL; DIFFUSION; URANIUM; KINETICS; OXYGEN;

D O I：

10.1016/j.nucengdes.2012.03.037

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：

The plutonium redistribution model (PUREDI) calculates the steady-state and transient radial plutonium concentration as a function of the radial temperature profile and the time for mixed oxide fuels (MOX). In the context of developing a TRANSURANUS version for Gen-IV fast reactor fuels, PUREDI has been modified and extended to include the effects of the local power density profile and the oxygen-to-metal ratio on plutonium transport. The model has been extensively verified by means of specific numerical tests, and after incorporation in the TRANSURANUS fuel performance code, has been assessed on the basis of post irradiation examinations of the SUPERFACT experiment, showing a good agreement with the experimental data. (C) 2012 Elsevier B.V. All rights reserved.

引用

页码：149 / 155

页数：7

共 35 条

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[Anonymous], [No title captured]

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Babelot J.F., 1999, JRCITUTN9903

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