Abstract
Accidental release of gaseous or liquid effluents is a critical issue and of a greater concern to the nuclear industry when it comes to the protection of the public and the environment. The emphasis becomes paramount when the release involves particulate of radiation particles. This paper provides a comprehensive insight report on an account of a research investigation carried out in addressing a radiological safety issue of Ghana’s Miniature Neutron Source Reactor (MNSR) during its core conversion project. The amounts of Strontium-90 (Sr-90) and Krypton-85 (Kr-85) effluents presumably released from the reactor hall to the surroundings and the consequential emission radiation to the working area within a 200 m radius were analyzed for a six-month working period. The objective was to estimate specifically the approximate total effective dose equivalent (TEDE) of Sr-90 and Kr-85 by considering a conjectural accident scenario using a well-recognized and user-friendly known atmospheric dispersion model before the preparatory period. The maximum TEDE value recorded at a ground deposition value of 4.6E − 01 kBq/m2 was approximately 1.80E − 02 mSv and 4.90E − 4 mSv for Sr-90 and Kr-85, respectively, at a maximum distance of 0.1 km from the source. The estimated dose values recorded were found to be within the recommended regulatory safety limits of 50 mSv for onsite workers and 1 mSv for the general public. No adverse effect was experienced with respect to human health and the environment.
Highlights
In Ghana, the only nuclear research reactor currently in operation is the Ghana Research Reactor-1. e reactor is a miniature neutron source reactor of a Chinese origin
Most research and test reactors use uranium aluminum alloyed fuel which has been preferred in the past. e reason is that High Enriched Uranium (HEU) (∼90% U-235) allows for denser reactor core design. e design helps to attain a high value of core excess reactivity which gives room for varieties of experiments
From regulatory perspective, addressing possible radiological consequences has been tagged as the hallmark of a nuclear regulator. With this aim and in fulfillments of regulatory requirements, this paper provides a comprehensive insight report on investigations carried out in addressing radiological safety measures of Ghana’s Miniature Neutron Source Reactor (MNSR) during the going core conversion project. e amounts of Strontium-90 (Sr-90) and Krypton-85 (Kr-85) effluents presumably released from the reactor hall to the surroundings and the consequential emission radiation to the working area within a 200m radius were analyzed for a six-month working period. e idea was to estimate the approximate total effective dose equivalent (TEDE) value of Sr-90 and Kr-85 release and its effect by considering a conjectural accident scenario using the most reliable atmospheric dispersion code before the preparatory period
Summary
In Ghana, the only nuclear research reactor currently in operation is the Ghana Research Reactor-1 (notably termed as “GHARR-1”). e reactor is a miniature neutron source reactor of a Chinese origin. E reactor is a miniature neutron source reactor of a Chinese origin. It is a very compact kind of research reactor fueled with High Enriched Uranium (HEU) [1]. E reason is that HEU (∼90% U-235) allows for denser reactor core design. Because of its nuclear unique properties, HEU can be relatively used in a much simple way for nuclear explosive device [2]. It has become significantly dangerous with regard to potential use by state and nonstate actors with limited nuclear weapon expertise. Due to the fact that HEU has a 20 percent or higher concentration of Uranium-235 or is a fissile material of 80 percent or more Uranium-235, it has been considered as weapons-grade [3]
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