Published February 1986 | Version v1
Report Metadata-only

TRAC-BWR code development

Creators

  • 1. EG and G Idaho, Inc., Idaho Falls

Description

The development work on TRAC-BWR in 1985 concentrated on improved code efficiency. A preload processor was written to minimize core storage requirements. The first fast running version of TRAC-BF1 was created. Among the important new features of this code are: Courant-limit violating (fast running) numerics for all one-dimensional hydraulic components, 1-D neutron kinetics model, upgraded control systems and over 95% ANSI standard FORTRAN coding. System calculations with TRAC-BF1 have shown CPU time savings around 35% compared to TRAC-BD1/MOD1. TRAC-BF1 was documented in a one-volume manual and TRAC-BWR workshop was held in September 1985

Additional details

Publishing Information

Imprint Title
Thirteenth water reactor safety research information meeting: proceedings. Volume 5
Journal Page Range
p. 303-326.
Report number
NUREG/CP--0072-Vol.5

Conference

Title
13. water reactor safety research information meeting.
Dates
22-25 Oct 1985.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18002564
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; ONE-DIMENSIONAL CALCULATIONS; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; REACTOR KINETICS; REACTOR SAFETY; T CODES; TRANSIENTS
Descriptors DEC
ACCIDENTS; CONTROL SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; KINETICS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS