首页> 外文会议>International Conference on Nuclear Engineering(ICONE12) 2004 vol.1; 20040425-29; Arlington,VA(US) >ANALYSIS OF A TOTAL FLOW BLOCKAGE OF A FUEL ASSEMBLY IN A TYPICAL MTR RESEARCH REACTOR BY RELAP5/MOD3.3
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ANALYSIS OF A TOTAL FLOW BLOCKAGE OF A FUEL ASSEMBLY IN A TYPICAL MTR RESEARCH REACTOR BY RELAP5/MOD3.3

机译:用RELAP5 / MOD3.3分析典型MTR研究反应器中燃料组件的总堵塞。

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The main aim of the following study is to perform a safety analysis of the IAEA 10 MW MTR Pool Type Research Reactor. The reactor is core cooled and moderated by downward forced circulation of light water. The transient herein considered is the related to partial and total obstruction of a single Fuel Assembly (FA) cooling channel. Such event constitutes a severe accident for this type of reactor since it may lead to local dryout and eventually to loss of the FA integrity. Two cases are analysed to emphasize the severity of the accident. The first one is a partial blockage of a single FA considering four different obstruction levels: 50%, 75%, 85% and 95% of nominal flow area. The second one is an extreme scenario consisting of total blockage of the same FA. This study constitutes the first step of a larger work which consists in performing a 3D simulation using the Best Estimate coupled code technique. However, as a first approach the instantaneous reactor power is derived through the point kinetic calculation.
机译:以下研究的主要目的是对IAEA 10 MW MTR池式研究堆进行安全性分析。将反应堆堆芯冷却,并通过向下强制循环轻水进行调节。本文考虑的瞬变与单个燃料组件(FA)冷却通道的部分或全部阻塞有关。对于这种类型的反应器,此类事件构成严重事故,因为它可能导致局部变干并最终导致FA完整性丧失。分析了两个案例以强调事故的严重性。第一个因素是考虑四个不同的阻塞水平:单个流量的部分阻塞:名义流量面积的50%,75%,85%和95%。第二种是极端情况,包括同一FA的全部阻塞。这项研究构成了更大工作的第一步,该工作包括使用“最佳估计”耦合代码技术执行3D仿真。但是,第一种方法是通过点动力学计算得出瞬时反应堆功率。

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