An experiment‐based validation of a system code for prediction of passive natural circulation in sodium‐cooled fast reactor. (27th October 2020)

• Record Type: Journal Article
• Authors: Wang, Shibao; Zhang, Dalin; Liu, Yapeng; Wang, Chenglong; Qiu, Suizheng; Su, Guanghui; Tian, Wenxi
• Other Names: Şahin Sümer guestEditor.
• Is Part Of: International journal of energy research. Volume 45:Number 8(2021)
• Page Start: 12093
• Page End: 12109
• Publication Date: 2020-10-27
• Subjects: natural circulation -- residual heat removal -- safety analysis -- sodium‐cooled fast reactor; Power resources -- Periodicals; Power (Mechanics) -- Periodicals; Power resources -- Research -- Periodicals; 621.042
• DOI: 10.1002/er.6103
• Languages: English
• ISSNs: 0363-907X

Abstract

Summary: To evaluate residual heat removal capacity of next generation China sodium‐cooled fast reactor (SFR) and provide data for code validation, an integral natural circulation experiment was performed on a scaled water platform which had same structure with reactor primary system. A modular code THACS focusing on safety analysis of SFR was validated by this test. Some necessary development and verification for physical property, frictional loss, and heat transfer of water were carried out first. Whole simulation of an unprotected loss‐of‐flow (ULOF) case was divided into two phases and computation lasted until 5000 s of test time during second stage. Agreement in light of system temperature distribution in first stage provided a suitable initial condition for subsequent transient. Satisfied flow rate curve was reproduced with decaying pressure head and valve characteristic as input when pump was stopping. All natural circulation paths were predicted, including original flow in primary loop through main pipe and reversed flow in reactor vessel cooling system (RVCS). Transition to operative mode of direct heat exchanger (DHX) in direct reactor auxiliary cooling system (DRACS) and its cooling power were also forecasted successfully. This work means a significant advance for THACS in the field of engineering application of China SFR. Abstract : An integral water test was designed to test residual heat removal capacity of China sodium‐cooled fast reactor (SFR) by natural circulation. An unprotected loss of flow (ULOF) case was simulated by a safety analysis code THACS for SFR. Satisfied agreement of temperature and velocity distribution within forced flow stage were achieved and all natural circulation paths were predicted successfully, which forwards THACS a big step in the field of engineering application for China SFR.