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Radiological impact assessment of routine atmospheric releases of MAAMORA Nuclear Research Center (MNRC)

机译:MAAMORA核研究中心(MNRC)常规大气排放的放射学影响评估

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CNESTEN is the main national operator of nuclear facilities within the MAAMORA Nuclear Research Center (MNRC) in Morocco. MNRC is presently holding a radioisotopes production facility, radioactive waste treatment and storage facilities and several laboratories using nuclear techniques and radioactive sources. The construction of a TRIGA Mark II research reactor is still on going. In compliance with national regulations with regard of the licensing process, CNESTEN has performed a radiological impact assessment for the routine atmospheric releases of Maamora Nuclear Research Center facilities in order to obtain the first licence for environmental discharge. The objective of the study is to propose to the national nuclear safety authority the atmospheric release limits and conduct the assessment of radiological consequences to the population reference groups which will be compared to the 1 mSv regulatory annual limit to the public. A conservative estimation has been developed for: the source term of the annual atmospheric releases, the release conditions at the stacks, the local meteorological data, exposure pathways scenarios of population reference groups. The dose assessment has been performed using two different calculation codes: GASCON (France/Commissariat a l’Energie Atomique) and CAP88 (USA/Lawrence Livermore National Laboratory). Under the conditions and the assumptions related to the routine radioactive atmospheric releases of MNRC, both of the calculation codes had given comparable estimations of individual and collective effective doses to the members of the public. The highest individual effective dose is estimated to 6.80 × 10~(-4) mSv per year which represents 0.07% of the 1 mSv regulatory annual limit to the public.
机译:CNESTEN是摩洛哥MAAMORA核研究中心(MNRC)内主要的国家核设施运营商。 MNRC目前拥有放射性同位素生产设施,放射性废物处理和储存设施以及几个使用核技术和放射源的实验室。 TRIGA Mark II研究堆的建造仍在进行中。根据有关许可程序的国家法规,CNESTEN对Maamora核研究中心设施的日常大气排放进行了放射学影响评估,以获得第一份环境排放许可证。这项研究的目的是向国家核安全当局提出大气释放限值,并对人群参考人群进行放射学评估,并将其与公众每年1毫希沃特的监管年度限值进行比较。已经针对以下方面制定了一个保守的估计:年度大气释放的源项,烟囱的释放条件,当地气象数据,人口参照人群的暴露途径情景。剂量评估使用两种不同的计算代码进行:GASCON(法国/法国商业原子能)和CAP88(美国/劳伦斯·利弗莫尔国家实验室)。在与MNRC的常规放射性大气释放有关的条件和假设下,这两个计算代码都对公众提供了个人和集体有效剂量的可比估计。最高的个人有效剂量估计为每年6.80×10〜(-4)mSv,占公众1 mSv监管年度限制的0.07%。

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