Simulation of Loss-of-Coolant Accident in Spent Fuel Pool with ASTEC Code

被引：0

作者：

Kljenak, Ivo ^{[1
]}

Matkovic, Marko ^{[1
]}

机构：

[1] Jozef Stefan Inst, Reactor Engn Div, Jamova Cesta 39, SI-1000 Ljubljana, Slovenia

来源：

26TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2017) | 2017年

基金：

欧盟第七框架计划;

关键词：

D O I：

暂无

中图分类号：

O414.1 [热力学];

学科分类号：

摘要：

A loss-of-coolant accident in a spent fuel pool (SFP) model, based on the SFP of the unit 4 of the Fukushima Daiichi nuclear power plant (Japan), was simulated with the ASTEC code. The specific phenomena concerning fuel rods were simulated using the parts of the code, originally intended for simulating phenomena in the reactor core. The results of the simulation, including the timeline of events, the peak cladding temperatures and the mass of generated hydrogen, are presented.

引用

页数：8

共 7 条

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