Published February 1992 | Version v1
Report Metadata-only

Trends in BWR transient analysis

Creators

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

Description

While boiling water reactor (BWR) analysis methods for transient and loss of coolant accident analysis are well established, refinements and improvements continue to be made. This evolution of BWR analysis methods is driven by the new applications. This paper discusses some examples of these trends, specifically, time domain stability analysis and analysis of the simplified BWR (SBWR), General Electric's design approach involving a shift from active to passive safety systems and the elimination/simplification of systems for improved operation and maintenance

Additional details

Publishing Information

Imprint Title
Seventh international RETRAN conference: Proceedings
Imprint Pagination
650 p.
Journal Page Range
p. 2.31-2.38.
Report number
EPRI-TR--100361

Conference

Title
7. international RETRAN conference.
Dates
15-18 Sep 1991.
Place
New Orleans, LA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24019552
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AFTER-HEAT REMOVAL; BWR TYPE REACTORS; CONTAINMENT SYSTEMS; EPRI; HEAT TRANSFER; HYDRAULICS; IDAHO NATIONAL ENGINEERING LAB; LOSS OF COOLANT; NEUTRON FLUX; O CODES; PROBABILITY; REACTOR CORES; REACTOR KINETICS; REACTOR SAFETY; REACTOR STABILITY; S CODES; STANDARDIZATION; STRATIFICATION; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE; TRANSIENTS; TWO-PHASE FLOW; US NRC; VOID FRACTION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINMENT; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; KINETICS; NATIONAL ORGANIZATIONS; POWER REACTORS; RADIATION FLUX; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; STABILITY; THERMAL REACTORS; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-9109388--.