会议专题

Conceptual Design of the Safety System for a SCWR Fuel Qualification Test

The test of a small scale fuel assembly operated with supercritical water in a critical arrangement is planned to be performed in the LVR-15 reactor of the Research Centre Rez (UJV), Czech Republic. It shall include 4 fuel rods of 60cm length inside a pressure tube to be operated at 25 Mpa pressure at the peak power conditions of the European High Performance Light Water Reactor concept. The test section is connected with a closed supercritical water loop at 300℃, and a recuperator is increasing the coolant temperature at the test section inlet to hot channel conditions of the evaporator of the above mentioned reactor. This paper describes the safety system needed to run the supercritical water loop. Like a boiling water reactor, it includes a depressurization system, a low pressure coolant injection system and an emergency coolant injection system to remove the residual heat safely in case of accidents. Numerical simulations with the system code APROS have been performed to check the system performance in case of a loss of coolant accident, a pump trip and a coolant bypass. The fuel section is expected to remain sufficiently cooled during any of these accident scenarios.

Supercritical Water Cooled Reactor Safety System Fuel Qualification Test

R. Schneider M. Schlagenhaufer T. Schulenberg

Karlsruhe Institute of Technology Institute for Nuclear and Energy Technologies 76021 Karlsruhe, Germany

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

1294-1303

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)