Citation

Dennis H, Grant C, Preston J. Appl. Radiat. Isot. 2017; 129: 152-155.

Affiliation

International Centre for Environmental and Nuclear Sciences, 2 Anguilla Close, University of the West Indies, Mona, Kingston 7, Jamaica. Electronic address: john.preston@uwimona.edu.jm.

Copyright

(Copyright © 2017, Elsevier Publishing)

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.

Copyright © 2017 Elsevier Ltd. All rights reserved.

Language: en

Keywords

Criticality safety; Highly-enriched uranium; Radiation shielding; Research reactor; Spent fuel