A BWR fuel assembly design for efficient use of plutonium in thorium–plutonium fuel
Artikel i vetenskaplig tidskrift, 2013

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.

Plutonium incineration

High burnup



Boiling water reactor

High moderation

Fuel assembly design


Klara L Insulander Björk

Chalmers, Teknisk fysik, Nukleär teknik

Progress in Nuclear Energy

0149-1970 (ISSN)

Vol. 65 56-63


Hållbar utveckling


Annan teknik

Annan fysik





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