Utilization of nuclear waste plutonium and thorium mixed fuel in candu reactors

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Date

2016

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Wiley

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Department of Mechanical Engineering
(2016)
The Mechanical Engineering Doctoral Program has started in 2016-2017 academic year. We have highly qualified teaching and research faculty members and strong research infrastructure in the department for graduate work. Research areas include computational and experimental research in fluid and solid mechanics, heat and mass transfer, advanced manufacturing, composites and other advanced materials. Our fundamental mission is to train engineers who are able to work with advanced technology, create innovative approaches and authentic designs, apply research methods effectively, conduct research and develop high quality methods and products in space, aviation, defense, medical and automotive industries, with a contemporary education and research infrastructure.

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Abstract

Spent nuclear fuel out of conventional light water reactors contains significant amount of even plutonium isotopes, so called reactor grade plutonium. Excellent neutron economy of Canada deuterium uranium (CANDU) reactors can further burn reactor grade plutonium, which has been used as a booster fissile fuel material in form of mixed ThO2/ PuO2 fuel in a CANDU fuel bundle in order to assure reactor criticality. The paper investigates incineration of nuclear waste and the prospects of exploitation of rich world thorium reserves in CANDU reactors. In the present work, the criticality calculations have been performed with 3-D geometrical modeling of a CANDU reactor, where the structure of all fuel rods and bundles is represented individually. In the course of time calculations, nuclear transformation and radioactive decay of all actinide elements as well as fission products are considered. Four different fuel compositions have been selected for investigations: 95% thoria (ThO2) + 5% PuO2,. 90% ThO2 + 10% PuO2,. 85% ThO2 + 15% PuO2 and. 80% ThO2 + 20% PuO2. The latter is used for the purpose of denaturing the new U-233 fuel with U-238. The behavior of the criticality k8 and the burnup values of the reactor have been pursued by full power operation for similar to 10 years. Among the investigated four modes, 90% ThO2 + 10% PuO2 seems a reasonable choice. This mixed fuel would continue make possible extensive exploitation of thorium resources with respect to reactor criticality. Reactor will run with the same fuel charge for similar to 7 years and allow a fuel burnup similar to 55 GWd/ t. Copyright (C) 2016 John Wiley & Sons, Ltd.

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Keywords

CANDU reactors, thorium, nuclear waste plutonium, high fuel burnup, long operation time

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Citation

11

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Q1

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Q1

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Volume

40

Issue

14

Start Page

1901

End Page

1907

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