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The design and evaluation of a passively cooled containment for a high-rating pressurized water reactor

机译:高压压水堆被动冷却安全壳的设计与评估

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An integrated pressurized water reactor (PWR) containment was conceptualized that allows heat to be rejected passively to the environment. The proposed containment is based on the demonstrated Ebasco Waterford 3 design. The secondary concrete shell was equipped with inlet and outlet vents that create an air-convection annulus. These vents also permit the submersion of the lower part of the primary containment into an external water pool. An internal water pool located at the bottom of the lower containment was added to increase in-containment heat storage. The performance of the proposed passively cooled containment was evaluated using a subdivided volume code, GOTHIC version 3.4e; the relative novelty of subdivided volume analyses for containment performance evaluation requires experimental verification of principal code predictions. Two experiments were carried out; one to test the performance of the external moat, and one to verify the code's ability to predict thermal-stratification inside the containment. To improve the subdivided-volume simulation of convection-related parameters, a modeling technique (boundary layer flow approximation) was devised. Finally, the behavior of the proposed containment was evaluated for the worst-case large break loss of coolant accident and the worst-case main steam line break accident. Peak pressures remained below 0.45 MPa during both transients; internal wall pressure differences, equipment qualification temperatures, pressure restoration time also remained below design limits. The mitigation capability of hydrogen recombiners was also evaluated.
机译:集成式压水堆(PWR)密闭容器的概念化设计使热量可以被动地散发到环境中。拟议的遏制措施是基于经过验证的Ebasco Waterford 3设计。第二混凝土外壳配有入口和出口通风孔,可形成空气对流环空。这些通风孔还允许将初级安全壳的下部浸入外部水池中。添加了位于下部安全壳底部的内部水池,以增加安全壳内的热量存储。拟议的被动冷却安全壳的性能使用细分的体积代码GOTHIC版本3.4e进行了评估;用于容量性能评估的细分体积分析的相对新颖性要求对主代码预测进行实验验证。进行了两个实验。一种是测试外部护城河的性能,另一种是验证代码预测安全壳内部热分层的能力。为了改进对流相关参数的细分体积模拟,设计了一种建模技术(边界层流量近似)。最后,针对最坏情况下的冷却剂大断裂损失事故和最坏情况下的主蒸汽管线断裂事故,评估了所建议的安全壳的行为。在两个瞬态过程中,峰值压力均保持在0.45 MPa以下。内壁压力差,设备合格温度,压力恢复时间也保持在设计极限以下。还评估了氢重组子的缓解能力。

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