Radiation source terms of MYRRHA reactor components and equipment

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Date

2016

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Journal ISSN

Volume Title

Publisher

Pergamon-elsevier Science Ltd

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Organizational Unit
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

In-vessel structural components of nuclear reactors are subject to prompt and residual neutron and photon activation. The MYRRHA fast spectrum facility, when operated in sub critical mode, suffers additional activation due to a wide range of energetic particles produced in the interactions of 600 MeV-primary protons with matter. The purpose of this work was to assess the source term (activation, heating and induced radiation level) of ex core equipment and components located inside the reactor vessel. Numerous stainless steel samples uniformly distributed inside the vessel have been used to simulate the activation of equipment in order to take into account the perturbation of the neutron spectrum caused by structural materials of components and equipment. The calculated quantities were prompt and residual activation, heating, radiation dose and radiation damage. The calculations were carried out with the ALEPH2 depletion code which invokes the MCNPX code for radiation transport. Copyright (C) 2016, Hydrogen Energy Publications, LLC. Published by Elsevier Ltd. All rights reserved.

Description

Van den Eynde, Gert/0000-0002-4728-4456; Stankovskiy, Alexey/0000-0003-1837-023X; celik, yurdunaz/0000-0002-9211-8510

Keywords

MYRRHA, Reactor vessel, MCNPX, Activation, ALEPH2

Turkish CoHE Thesis Center URL

Citation

2

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Q1

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Source

17th International Conference on Emerging Nuclear Energy Systems (ICENES) -- OCT 04-08, 2015 -- Istanbul, TURKEY

Volume

41

Issue

17

Start Page

7213

End Page

7220

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