DocumentCode
2112673
Title
Safety Analysis for IPWR under Over-Pressurizing Accident Conditions
Author
Dai Shoubao ; Peng Minjun
Author_Institution
Coll. of Nucl. Sci. & Technol., Harbin Eng. Univ., Harbin, China
fYear
2010
fDate
28-31 March 2010
Firstpage
1
Lastpage
5
Abstract
In this paper an integral pressurized water reactor (IPWR) has 100 MW capacity with passive safety features. The design of IPWR focuses on enhancing the safety and reliability of the reactor by employing inherent safety features such as low core power density, elimination of large break loss of coolant accident, etc. In addition, in order to prevent the progression of emergency situations into accident, IPWR is provided with a number of engineered safety features such as passive residual heat removal system (PRHRS).This paper presents an overview of the IPWR design, and results of over-pressure accident analyses. The results of the accident analyses show that IPWR provides the inherent over-pressure protection capability for design basis accidents without actuation of any protection devices such as safety valves, rupture disks, etc.
Keywords
fission reactor cooling; fission reactor safety; light water reactors; power generation protection; power generation reliability; IPWR; integral pressurized water reactor; over-pressurizing accident conditions; passive residual heat removal system; power 100 MW; safety analysis; Accidents; Coolants; Design engineering; Heat engines; Inductors; Power engineering and energy; Protection; Reliability engineering; Safety devices; Valves;
fLanguage
English
Publisher
ieee
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
Type
conf
DOI
10.1109/APPEEC.2010.5449208
Filename
5449208
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