Published 1993 | Version v1
Book Metadata-only

Calculations of severe accident progression in the General Electric Simplified Boiling Water Reactor

Creators

  • 1. General Electric, Nuclear Energy, San Jose, CA (United States). Advanced Reactor Programs
  • 2. Gabor Kenton and Associates, Inc., Westmont, IL (United States)
  • 3. Idaho National Engineering Lab., Idaho Falls, ID (United States)

Description

General Electric is designing a new nuclear power plant: the Simplified Boiling Water Reactor (SBWR). The SBWR is a passive plant in which the core cooling and decay heat removal safety systems are driven by gravity. To model the plant response to severe accidents, MAAP-SBWR, an advanced version of the Modular Accident Analysis Program (MAAP), has been developed. The main feature of the new code is a flexible containment model. The challenges in modeling the SBWR, the code structure and models, and a sample application to the SBWR are discussed

Part of:
2nd ASME-JSME international conference on nuclear engineering -- 1993

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-0636-7
Imprint Title
2nd ASME-JSME international conference on nuclear engineering -- 1993
Imprint Pagination
770 p.
Journal Page Range
p. 463-470.

Conference

Title
2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
Dates
21-24 Mar 1993.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25058701
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CONTAINMENT BUILDINGS; ENGINEERED SAFETY SYSTEMS; GAS FLOW; GRAVITATION; M CODES; MATHEMATICAL MODELS; REACTOR ACCIDENTS
Descriptors DEC
ACCIDENTS; BUILDINGS; COMPUTER CODES; CONTAINMENT; ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-930352--.