A BWR fuel assembly design for efficient use of plutonium in thorium-plutonium fuel

被引：13

作者：

Bjork, Klara Insulander ^{[1
,2
]}

机构：

[1] Thor Energy, NO-0255 Oslo, Norway

[2] Chalmers, Dept Appl Phys, Div Nucl Engn, SE-41296 Gothenburg, Sweden

来源：

PROGRESS IN NUCLEAR ENERGY | 2013年 / 65卷

关键词：

Thorium; Plutonium; Boiling water reactor; Fuel assembly design; High moderation; High burnup; Plutonium incineration; WATER-REACTORS;

D O I：

10.1016/j.pnucene.2013.01.010

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 objective of this study is to develop an optimized BWR fuel assembly design for thorium-plutonium fuel. In this work, the optimization goal is to maximize the amount of energy that can be extracted from a certain amount of plutonium, while maintaining acceptable values of the neutronic safety parameters such as reactivity coefficients, shutdown margins and power distribution. The factors having the most significant influence on the neutronic properties are the hydrogen-to-heavy-metal ratio, the distribution of the moderator within the fuel assembly, the initial plutonium fraction in the fuel and the radial distribution of the plutonium in the fuel assembly. The study begins with an investigation of how these factors affect the plutonium requirements and the safety parameters. The gathered knowledge is then used to develop and evaluate a fuel assembly design. The main characteristics of this fuel design are improved Pu efficiency, very high fractional Pu burning and neutronic safety parameters compliant with current demands on UOX fuel. (C) 2013 Elsevier Ltd. All rights reserved.

引用

页码：56 / 63

页数：8

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