Application of RELAP5/MOD4.0 Code in a Fluoride Salt-Cooled High-Temperature Test Reactor

摘要

A fluoride salt-cooled high-temperature test reactor concept named TMSR-SF was proposed by the Center for Thorium Molten Salt Reactor (TMSR) Research, Chinese Academy of Sciences (CAS) in 2012. The fuels of the TMSR-SF are same as the high-temperature graphite-matrix coated-particle fuel which developed for HTR-10 (a helium-cooled high-temperature reactors) with fuel failure temperature beyond 1600°C.TMSR-SF can operate at a low pressure due to the fluoride salt coolant characteristics TMSR-SF as a test reactor will be built by the end of 2017. The reactor system safety analysis is a key issue to the TMSR-SF in the development of the TMSR-SF technology. Transient analysis for the reactor will be done by the RELAP/MOD4.0 code. RELAP5 code is a light water reactor transient analysis code, so it should be amended to meet the need of the fluoride salt-cooled high-temperature test reactor. The new heat transfer correlation for the fluoride salt-cooled high-temperature pebble bed reactor as a module was inserted into RELAP/MOD4.0 by the Center for Thorium Molten Salt Reactor of CAS. And also a LOFC accident is simulated by the molten salt reactor module of RELAP5/MOD4.0 code in this paper to study the influence of the new heat transfer correlation to the analysis of the accident.