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ID: 077015

Feasibility of converting Russian icebreaker reactors from HEU / Diakov, Anatoli C; Dmitriev, Alexander M; Kang, Jungmin; Shuvayev, Alexey M

Kang, Jungmin	Journal Article
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Publication

2007.

Summary/Abstract

A considerable amount of experience has been accumulated in converting compact research reactors from highly-enriched uranium (HEU) to low-enriched uranium (LEU). Although the details of naval-reactor design are closely held military secrets, during the Gorbachev period, the Soviet Union supplied the Norwegian government with some basic data, including the dimensions and 235U content of the core of the HEU fueled KLT-40 reactor used in some Russian nuclear-powered icebreakers. A group of Norwegian analysts used this information to develop a simple model of the KLT-40 core. We have calculated the neutronics behaviors of variants of these core models as a function of 235U burnup and conclude that the reactors could be fueled with LEU without loss of core life. We also show that simplified infinite-core calculations can be used for such studies

Key Words

Nuclear Material ; Uranium Fuel ; Russia Icebreaker Reactor ; Highly-Enriched Uranium ; HEU ; Low-Enriched Uranium ;
LEU

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ID: 077013

On the proliferation potential of uranium fuel for research reactors at various enrichment levels / Glaser, Alexander

Glaser, Alexander	Journal Article
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Publication

2006.

Summary/Abstract

This article reviews the rationale of selecting an enrichment of just less than 20% (low-enriched uranium) as the preferred enrichment level for research reactor fuel in order to minimize overall proliferation risks. The net strategic value of the nuclear material associated with reactor operation is evaluated for a variety of enrichment levels, ranging from slightly enriched to weapon-grade fuel. To quantify the proliferation potential, both the demand of fresh uranium fuel as well as the plutonium buildup in the irradiated fuel are estimated via cell burnup calculations. The analysis confirms the usefulness of the current enrichment limit and challenges a recent trend to reconsider fuel enrichment levels between 20% and 50% for new research reactor projects

Key Words

Nuclear Material ; Uranium Fuel

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ID: 020569

Public health risks of substituting mixed oxide for uranium fuel in pressurized-water reactor / Lyman Edwin S

2001

Lyman Edwin S	Article
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Publication	2001.
Description	33-79

Key Words

Nuclear Reactor ; Uranium Fuel ; Water Reactors

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