Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Main pipe rupture accident analysis for the Chinese experimental fast reactor

Yang Hongyi; Xu Mi (China Institute of Atomic Energy (CIAE), Beijing (China))

Abstract

The main pipe rupture accident is the most serious one for the loss of coolant accident of pool type sodium cooled Fast Breeder Reactor (FBR). To simulate this accident, a model is developed based on the OASIS code, which is a French fast reactor system safety analysis code. To abide by the strict accident analysis principles, the main pipe rupture accident is calculated for various position of the pipe. Accident sequence and key parameters, including the fuel cladding temperature of reactor, are obtained for each case. The calculation results show that the fuel cladding temperature is below the safety limitation and the coolant temperature is lower then the saturation temperature of sodium in all cases. (author)

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key words: fuel-cladding interactions; lmfbr type reactors; o codes; pipes; primary coolant circuits; ruptures; safety analysis; safety margins; sodium; temperature dependence; breeder reactors; epithermal reactors; fast reactors; fbr type reactors; liquid metal cooled reactors;
Reference:
Proceedings of a technical meeting held in Kalpakkam, India 13-17 January 2003
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1406, pp:35-45