使用MCNP-ORIGEN激活自动化工具计算高温气冷堆的关闭剂量率

Roberto Fairhurst-Agosta, Tomasz Kozlowski
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引用次数: 0

摘要

高温气冷堆(htgr)与目前的轻水堆(LWR)有许多不同的特点,潜在的退役策略应该考虑到这些特点。适当的关闭剂量率表征可以建立一个合适的策略。方法利用MCNP- origen激活自动化工具和MCNP重复结构对三结构各向同性(TRISO)粒子作为衰变辐射源进行显式建模,建立了一种新的关闭剂量率计算能力。结果运用该能力进行了3次演练,并对其结果进行了讨论。前两个练习验证并演示了工作流。第三部分提出了一种高温气冷微堆的退役策略,并从停堆剂量率的角度研究了其可行性。计算结果显示,经过三个月的冷却后,反应堆堡垒的剂量率图高于40毫西弗/小时。研究结果表明,基于将反应堆置于安全关闭状态并冷却三个月,然后移除各种组件并提取燃料组件的退役策略可能不足以减少不必要的人员暴露。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Shutdown dose rate calculations in high-temperature gas-cooled reactors using the MCNP-ORIGEN activation automation tool
Background High-temperature gas-cooled reactors (HTGRs) have many distinct features from the current light water reactor (LWR) fleet, and potential decommissioning strategies should take them into consideration. The proper characterization of the shutdown dose rates can establish a suitable strategy. Methods This article introduces a new shutdown dose rate calculation capability that relies on the MCNP-ORIGEN activation automation tool and the MCNP repeated structures to explicitly model the TRistructural ISOtropic (TRISO) particles as decay radiation sources. Results Three exercises are conducted with this capability, and their results discussed. The first two exercises verify and demonstrate the workflow. The third exercise proposes a decommissioning strategy for a high-temperature gas-cooled microreactor and studies its feasibility from the shutdown dose rate standpoint. The calculations yield a dose rate map above at the reactor citadel after a three month cool-down, showing values above 40 mSv/h. Conclusions The findings imply that the decommissioning strategy based on placing the reactor in a safe shutdown state and allowing it to cool down for three months before removing various components and extracting the fuel assemblies, may not be sufficient to minimize unnecessary exposure of personnel.
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