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

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ID: 32299
2017
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Ranked #38 of 55 articles by views in Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine

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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.
Reference Key
dennis2017radiationapplied Use this key to autocite in the manuscript while using SciMatic Manuscript Manager or Thesis Manager
Authors Dennis, Haile;Grant, Charles;Preston, John;
Journal Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine
Year 2017
DOI
S0969-8043(17)30576-6
URL
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