TRAC (Transient Reactor Analysis Code) support software

Technical Report · Wed Jun 01 04:00:00 EDT 1988

OSTI ID:6941763

Jenks, R P; Martinez, V

This manual provides users of the Transient Reactor Analysis Code (TRAC) with information about computer codes that can be used to support their analysis efforts. These codes are collectively referred to as TRAC support software. Specifically, documentation is provided to allow users to implement, apply, and interpret the output of the support software that is available. The TRAC code is an advanced best-estimate code for analyzing transients in thermal-hydraulic systems. Considerable input data are required for modeling a large thermal-hydraulic system and considerable output data are produced from the computer calculation for analysis: the support software assists users in their management of both the input and the output data. The four codes described are central to the efficient and effective use of the TRAC code. EXCON is a TRAC graphics file postprocessor that converts the TRAC graphics output files into component-oriented input data files for use with TRAP. TRAP is an extensive plotting package that allows users to produce a range of plots from quick draft-quality graphs for fast examination of results to final presentation-quality graphics for more formal documentation requirements. Extract is a powerful support code that reads a TRAC dump file and generates ''extracted information'' for building TRAC input decks with the latest values for system conditions. EXTRACT is particularly useful and cost effective for analyses that require multiple parametric calculations. CVRT converts TRAC-PF1/MOD1 and early-version MOD2 input decks into current TRAC-PF1/MOD2 input decks.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Accident Analysis; Los Alamos National Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6941763
• Report Number(s): NUREG/CR-5071; LA-11214-MS; ON: TI88013746
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
COMPUTER CODES
COMPUTER PROGRAM DOCUMENTATION
E CODES
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
THERMAL POWER PLANTS
TRANSIENTS