Development of time dependent safety analysis code for plasma anomaly events in fusion reactors

作     者：Honda, T Bartels, HW Uckan, NA Seki, Y Okazaki, T 

作者机构：ITER JOINT CENT TEAM SAN DIEGO CA USA OAK RIDGE NATL LAB OAK RIDGE TN 37831 USA JAPAN ATOM ENERGY RES INST NAKA FUS RES ESTAB NAKA IBARAKI 31101 JAPAN 

出 版 物：《JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY》 (核科学与技术杂志)

年 卷 期：1997年第34卷第3期

页      面：229-239页

核心收录：

学科分类：08[工学] 0827[工学-核科学与技术] 

主　　题：ITER plasma anomaly events safety analysis computer code plasma dynamics thermal analysis beta limit density limit confinement transition in-vessel components 

摘      要：A safety analysis code SAFALY has been developed to analyze plasma anomaly events in fusion reactors, e.g., a loss of plasma control. The code is a hybrid code comprising a zero-dimensional plasma dynamics and a one-dimensional thermal analysis of in-vessel components. The code evaluates the time evolution of plasma parameters and temperature distributions of in-vessel components. As the plasma-safety interface model, we proposed a robust plasma physics model taking into account updated data for safety assessment. For example, physics safety guidelines for beta limit, density limit and H-L mode confinement transition threshold power, etc. are provided in the model. The model of the in-vessel components are divided into twenty temperature regions in the poloidal direction taking account of radiative heat transfer between each surface of each region. This code can also describe the coolant behavior under hydraulic accidents with the results by hydraulics code and treat vaporization (sublimation) from plasma facing components (PFCs). Furthermore, the code includes the model of impurity transport form PFCs by using a transport probability and a time delay. Quantitative analysis based on the model is possible for a scenario of plasma passive shutdown. We examined the possibility of the code as a safety analysis code for plasma anomaly events in fusion reactors and had a prospect that it would contribute to the safety analysis of the International Thermonuclear Experimental Reactor (ITER).