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Radiation and criticality safety analyses for the highly-enriched uranium core removal from a research reactor.

作者信息

Dennis Haile, Grant Charles, Preston John

机构信息

International Centre for Environmental and Nuclear Sciences, 2 Anguilla Close, University of the West Indies, Mona, Kingston 7, Jamaica.

出版信息

Appl Radiat Isot. 2017 Nov;129:152-155. doi: 10.1016/j.apradiso.2017.08.025. Epub 2017 Aug 31.

DOI:10.1016/j.apradiso.2017.08.025
PMID:28863288
Abstract

Analysis was performed to estimate radiation levels during removal and packaging of the highly-enriched uranium core of the JM-1 SLOWPOKE-2 research reactor. Due to severe limitations of space in and around the reactor pool, the core could not be removed in the conventional manner as was done for previous SLOWPOKE defuelling operations. A transfer shield, with a balance between shielding efficacy, volume and weight was designed. Fuel depletion, Monte Carlo shielding and criticality calculations were performed. Comparisons of measured and calculated dose rates as well as results of the criticality safety assessment are presented. The designed transfer shield reduced the calculated unshielded dose rate from 29Sv/h to 8mSv/h. The maximum calculated effective neutron multiplication factor of approximately 0.89 was below the 0.91 upper subricital limit.

摘要

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