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.

中文翻译：

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推测性事故情景下加纳MNSR中锶和K释放的影响

气体或液体流出物的意外释放是一个关键问题，在保护公众和环境方面，是核工业更加关注的问题。当释放涉及辐射微粒时，重点变得尤为重要。本文针对加纳的微型中子源反应堆（MNSR）在其核心转换项目中为解决放射安全问题而进行的一项研究调查提供了全面的见解报告。分析了从反应堆大厅释放到周围的Strontium-90（Sr-90）和Krypton-85（Kr-85）废水的量以及向200 m半径内工作区域的相应发射辐射一个月的工作时间。目的是通过在准备阶段之前使用公认的且易于使用的已知大气弥散模型来考虑一个推测性事故情景，从而具体估算Sr-90和Kr-85的近似总有效剂量当量（TEDE）。在地面沉积值为4.6E − 01 kBq / m时记录的最大TEDE值 对于Sr-90和Kr-85，在距源的最大距离为0.1 km时，²分别约为1.80 E  -02 mSv和4.90 E -4 mSv。发现记录的估计剂量值在建议的监管安全限值之内，即现场工作人员50 mSv，一般公众1 mSv。在人类健康和环境方面未发生不利影响。