Title :
Small-Break Loss of Coolant Accident Analysis of the Integrated Pressurized Water Reactor
Author :
Liu, Jiange ; Peng, Minjun ; Zhang, Zhijian ; Jiang, Liguo
Author_Institution :
Nucl. Power Simulation Res. Center, Harbin Eng. Univ., Harbin, China
Abstract :
The pressurizer vapour space small-break loss of coolant accident is analyzed based on the nuclear thermal hydraulic transient analysis software RELAP5/SCDAP/MOD3.4 code. Transient characteristics of the Integrated Pressurized Water Reactor (IPWR) system pressure, core temperature, mass flow rate, reactor vessel water level are achieved. The influences of three different break areas are also studied and the conclusion is consistent with local experiment conclusion. The results show that the safety system of the IPWR can make sure the reactor core is under the water after the accident happens and the passive residual heat removal system can remove the core heat.
Keywords :
fission reactor accidents; fission reactor cooling; light water reactors; IPWR system; Integrated Pressurized Water Reactor; RELAP5/SCDAP/MOD3.4 code; core temperature; mass flow rate; nuclear thermal hydraulic transient analysis software; passive residual heat removal system; reactor vessel water level; small break loss of coolant accident; Accidents; Coolants; Fatigue; Inductors; Regulators; Safety; Space technology; Temperature; Valves; Water heating;
Conference_Titel :
Power and Energy Engineering Conference (APPEEC), 2010 Asia-Pacific
Conference_Location :
Chengdu
Print_ISBN :
978-1-4244-4812-8
Electronic_ISBN :
978-1-4244-4813-5
DOI :
10.1109/APPEEC.2010.5449161
