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Safety analysis of a homogeneous SLOWPOKE reactor.

机译：均质SLOWPOKE反应堆的安全性分析。

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摘要

An opportunity is presented with the approaching end of some of the SLOWPOKE-2 research reactors' design life, which consists of replacing the current heterogeneous core with a homogeneous assembly that would allow the extraction of radioisotopes (such as 99Mo) for nuclear medicine and other applications. The present research aims at continuing the safety analysis of the proposed homogeneous assembly, most notably in assessing its inherent safety characteristics with respect to factors such as void fraction of the homogeneous fuel-moderator mixture and thermalhydraulic effects at various temperatures.;Several possible accident scenarios are considered, and resulting modelled reactivities demonstrate that negative feedback would be expected in transients. The homogeneous SLOWPOKE is shown to behave in a consistently self-limiting fashion following reactivity changes, ranging from moderate to severe in magnitude.;Key words. Safety Analysis, Homogeneous, SLOWPOKE, MCNP-5, WIMS-AECL 3.1, COMSOL MultiphysicsRTM.;Neutronic modelling of the reactor is accomplished using the Los Alamos National Laboratories' MCNP 5 code and Atomic Energy of Canada Limited's WIMS-AECL 3.1 code for the determination of the reactor's reactivity and neutron flux shape, while COMSOL MultiphysicsRTM is used for the thermalhydraulics modelling. In parallel with the safety analysis, the design of the reactor is further improved in terms of increase to both the expected service life of the reactor vessel and the core volume for added radioisotope production.
机译：SLOWPOKE-2研究堆的某些设计寿命即将结束时，提供了一个机会，其中包括用均质组件替换当前的异质堆芯，从而可以提取放射性同位素（例如99Mo）用于核医学和其他领域。应用程序。本研究旨在继续对提议的均质组件进行安全性分析，尤其是在评估其固有安全性方面，例如在各种温度下均质燃料-减速剂混合物的空隙率和热工液压效应等因素。考虑到了这一点，结果建模的反应性证明在瞬态中会产生负反馈。均一的SLOWPOKE在反应性变化后表现出一致的自限性行为，反应性的变化范围从中等到严重。安全分析，均质，慢速，MCNP-5，WIMS-AECL 3.1，COMSOL MultiphysicsRTM .;使用Los Alamos国家实验室的MCNP 5代码和加拿大原子能有限公司的WIMS-AECL 3.1代码完成反应堆的中子建模确定反应堆的反应性和中子通量形状，而COMSOL MultiphysicsRTM用于热工水力模型。与安全分析同时，在增加反应堆容器的预期使用寿命和增加放射性同位素生产的堆芯体积方面，进一步改进了反应堆的设计。

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  • 作者

    Gagnon, Rejean Luc.;

  • 作者单位

    Royal Military College of Canada (Canada).;

  • 授予单位 Royal Military College of Canada (Canada).;
  • 学科 Chemistry Biochemistry.;Engineering Nuclear.
  • 学位 M.A.Sc.
  • 年度 2009
  • 页码 145 p.
  • 总页数 145
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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