The source term for the JRTR research reactor is derived under an assumed hypothetical severe accident resulting in generation of the most severe consequences. The reactor core is modeled based on the reactor technical design specifications, and the fission products inventory is calculated by using the SCALE/TRITON depletion sequence to perform burnup and decay analyses via coupling the NEWT 2-D transport lattice code to the ORIGEN-S fuel depletion code. Fifty radioisotopes contributed to the evaluation, resulting in a source term of 3.7 × 10¹⁴ Bq. Atmospheric dispersion was evaluated using the Gaussian plume model via the HOTSPOT code. The plume centerline total effective dose (TED) was found to exceed the IAEA limits for occupational exposure of 0.02 Sv; the results showed that the maximum dose is 200 Sv within 200 m from the reactor, under all the weather stability classes, after which it starts to decrease with distance, reaching 0.1 Sv at 1 km from the reactor. The radiation dose plume centerlines continue to the exceed international basic safety standards annual limit of 1 mSv for public exposure, up to 80 km from the reactor.

中文翻译：

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严重事故下JRTR研究堆的源项推导和放射性释放评估

JRTR研究堆的源术语是在假设的严重事故下得出的，该事故导致产生最严重的后果。根据反应堆技术设计规范对反应堆堆芯进行建模，并通过将NEWT 2-D传输晶格代码与ORIGEN-S燃料耦合，使用SCALE / TRITON耗尽序列进行燃烧和衰变分析，计算裂变产物存量耗尽代码。五十种放射性同位素有助于评估，因此源项为3.7×10 ¹⁴烧烤 使用高斯羽流模型通过HOTSPOT代码评估大气扩散。发现烟羽中心线总有效剂量（TED）超过了IAEA 0.02 Sv的职业暴露限值；结果表明，在所有天气稳定性等级下，反应堆200 m内的最大剂量为200 Sv，此后它随距离的增加而减小，在距离反应堆1 km处达到0.1 Sv。辐射剂量羽流中心线继续超过国际基本安全标准，即每年对公众暴露的极限为1 mSv，距离反应堆不超过80 km。