Published 1992 | Version v1
Book

Analysis of SBWR passive containment cooling following a LOCA

  • 1. General Electric Co., San Jose, CA (United States)

Description

A condensation heat transfer mechanism of long-term decay heat removal, the Passive Containment Cooling System (PCCS), has been incorporated into the design of the Simplified Boiling Water Reactor (SBWR). A second independent system, the Isolation Condenser condensation heat exchange system (ICS), may be used in conjunction with the PCCS to increase the rate of heat removal from the SBWR. TRACG (Transient Reactor Analysis Code) is used to evaluate the system behavior for long-term decay heat removal following a LOCA. The present analysis focuses on SBWR containment cooling with two possible combinations of the IC and PCC systems. Results of TRACG calculations show that: (1) the PCCS alone is adequate for decay heat removal: (2) containment cooling is mildly enhanced by operation of the ICS in conjunction with the PCCS. (author)

Part of:
ANP'92 international conference on design and safety of advanced nuclear power plants

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
ANP'92 international conference on design and safety of advanced nuclear power plants
Imprint Pagination
[2182 p.].
Journal Page Range
v. 3 p. 31.2/1-31.2/7.

Conference

Title
international conference on design and safety of advanced nuclear power plants.
Acronym
ANP'92
Dates
25-29 Oct 1992.
Place
Tokyo (Japan).

Optional Information

Notes
Imprint:Composed of four volumes.