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钠冷快堆碎片床迁移判据模型适用性分析

Applicability Analysis of Onset Model for Debris Bed Relocation in Sodium-Cooled Fast Reactor
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摘要 当钠冷快堆(SFR)发生堆芯解体事故(CDA)时,熔化后的堆芯燃料被冷却剂冷却固化成碎片颗粒,在堆芯下腔室堆积成碎片床。为保证碎片床内部的衰变热的有效移除以及熔融物堆内滞留(IVR)的有效实施,必须对碎片床迁移行为进行有效预测和模拟。研究人员基于颗粒受力平衡分析开发了碎片床迁移判据模型,以用于判断碎片床是否发生迁移。本文采用底部注气方法进行大量的碎片床迁移实验,并利用迁移判据模型对不同实验条件下的碎片床迁移行为进行计算和预测,进一步验证了所开发的碎片床迁移判据模型的合理性。 When the core disruptive accident(CDA) occurs in the sodium-cooled fast reactor(SFR), the melted core fuel is cooled and solidified into debris particles by the coolant, which accumulates in the lower plenum and forms the debris bed. In order to effectively remove the decay heat from the debris bed and implement the in-vessel corium retention(IVR), it is necessary to predict and simulate the relocation behavior of the debris bed. For this reason, Zhang et al. developed an onset model for judging the relocation of the debris bed based on the force balance analysis of the particle. In this paper, a large number of debris bed relocation experiments were carried out by bottom gas-injection method, and the relocation onset model was used to calculate and predict the relocation behavior of the debris bed under different experimental conditions, which further verified the applicability of the relocation onset model.
作者 滕春明 张斌 单建强 张熙司 曹永刚 Teng Chunming;Zhang Bin;Shan Jianqiang;Zhang Xisi;Cao Yonggang(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an,710049,China;State Key Laboratory of Multiphase Flow in Power Engineering,Xi’an Jiaotong University,Xi’an,710049,China;Reactor Engineering Technology Research Division,China Institute of Atomic Energy,Beijing,102413,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2021年第1期42-47,共6页 Nuclear Power Engineering
关键词 钠冷快堆 迁移判据模型 底部注气实验 模型验证 Sodium-cooled fast reactor Relocation onset model Bottom gas-injection experiment Model validation
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