Published 1984 | Version v1
Book Metadata-only

Application of TRAC-BD1/MOD1 to a BWR/4 feedwater control failure ATWS

Creators

  • 1. EG+G Idaho, Inc., Idaho Falls, ID

Description

The paper begins with a short description of the Transient Reactor Analysis Code for Boiling Water Reactors (TRAC-BWR), briefly mentioning some of its main features such as specific BWR models and input structure. Next, an input model of a BWR/4 is described, and, the assumptions used in performing an analysis of the loss of a feedwater controller without scram are listed. The important features of the calculated trends in flows, pressure, reactivity, and power are shown graphically and commented in the text. A comparison of some of the main predicted trends with the calculated results from a similar study by General Electric is also presented

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
Imprint Title
Proceedings of international nuclear power plant thermal hydraulics and operations topical meeting
Journal Page Range
p. A4-1-A4-6.

Conference

Title
International thermal hydraulics and plant operations topical meeting.
Dates
22-24 Oct 1984.
Place
Taipei, TW (China).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17078712
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ATWS; BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; FAILURES; HEAT TRANSFER; HYDRAULICS; LOSS OF FLOW; REACTIVITY; REACTOR COOLING SYSTEMS; REACTOR KINETICS; SYSTEM FAILURE ANALYSIS; T CODES; VALVES
Descriptors DEC
ACCIDENTS; CONTROL EQUIPMENT; COOLING SYSTEMS; DESIGN BASIS ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; KINETICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS