跳到主要导航 跳到搜索 跳到主要内容

RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor

  • Xi'an Jiaotong University

科研成果: 期刊稿件文章同行评审

19 引用 (Scopus)

摘要

The Fluoride-salt-cooled High temperature Reactors (FHRs) are an advanced concept using a novel combination of high-temperature coated-particle fuel, low-pressure fluoride-salt coolant and air-Brayton power conversion system. RELAP5, developed for the best-estimate transient simulation of light water reactors, is still recommended to perform safety analysis of FHRs during postulated accidents. Thermo-physical properties and transport properties of liquid and vapor fluoride salts are implemented into the RELAP5 MOD3.2 source code, through which the application of the RELAP5 MOD3.2 can be extended from the water-cooled reactors to the FHRs. Specific heat transfer correlations are also incorporated into the code for this type of reactors. A RELAP5 model is developed for the MK1 Pebble Bed Fluoride-Salt-Cooled High-Temperature Reactor (MK1 PB-FHR). Using the modified code, two basic postulated transients including the unprotected loss of forced circulation (ULOFC) and unprotected transient overpower (UTOP), are investigated to explore the safety characteristics of the MK1 PB-FHR. Results show that the core outlet temperature may exceed its limit in the ULOFC caused by two main pumps trip. It can be also concluded that the passive residual heat removal system can mitigate the consequences of the ULOFC. Results of the sensitivity analysis of the UTOP indicate that the reactor power and core temperatures show a linear increment trend versus the positive reactivity insertion.

源语言英语
页(从-至)504-515
页数12
期刊Annals of Nuclear Energy
101
DOI
出版状态已出版 - 1 3月 2017

学术指纹

探究 'RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor' 的科研主题。它们共同构成独一无二的学术指纹。

引用此