5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P1.163 Safety analysis of the helium cooling system for the HCSB blanket of CFETR

5 Sep 2016, 14:20
1h 40m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 163
Poster H. Fuel Cycle and Breeding Blankets P1 Poster session

Speaker

Shuai Wang (School of Nuclear Science and Technology)

Description

Chinese Fusion Engineering Test Reactor (CFETR) is an ITER-like fusion device that was proposed to achieve 200 MW fusion power, 30-50% duty time factor, and tritium self-sufficiency. As a candidate blanket concept for CFETR, a helium cooled solid breeder (HCSB) blanket was designed following the specific requirements. The helium cooling system (HCS) is an important ancillary system of HCSB blanket for CFETR. The preliminary design and description of HCS was already done while accident cases are investigated for the HCS.All components in the system are modeled as well as the main control strategy. Two typical operation modes for the HCS have been considered: a pulsed operation and a steady state operation. Three accident cases for each of the two operating modes are studied with RELAP5 including ex-vessel loss of coolant accident, loss of flow accident and failure of pressure control system.Ex-vessel loss of coolant accident caused by a double-ended pipe break of the HCS is considered as one of the most critical accidents. Loss of flow accident caused by the circulator seizure of the HCS is worth to study. The analysis of failure of pressure control system is critical for the pressure level in the system.Simulation results show that the design parameters of HCS is enough to sustain these accidents and to achieve the requirements of HCSB blanket. Key words: Safety analysis, RELAP5, HCS, HCSB blanket

Co-authors

Guangming Zhou (School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui, China) Hongli Chen (School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui, China) Shuai Wang (School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui, China)

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