Published 1987 | Version v1
Book

Fastrap

  • 1. Dipt. di Costruzioni Meccaniche e Nucleari, Via Diotisalvi, 2 56100 Pisa (Italy)

Description

The FASTRAP code has been developed with the aim of evaluating special transients (STs) and small break loss of coolant accidents (SB-LOCAs) in pressurized water reactors (PWRs) with U-tubes steam generators (SGs). In order to have fast running time, the code simplicity was a main objective of the work and it was obtained by adapting a fixed schematic structure for simulating PWR. The model includes features allowing to perform ST and SB-LOCA best estimate calculations (enthalpy transport, CCFL, HF and HEM models for critical two-phase flow rate evaluation, etc.); particular care has been devoted to the model of the pressurizer, represented by two nodes, whose volumes change during the transient. The FASTRAP code, written in FORTRAN77, has been designed to run on small computers and has a core storage need of less than 600 Kybtes. The code has been tested on IBM-3081 computer. Typical running time is one- hundred times shorter than real time; the set up of input data files is very easy. In order to assess the capability of the code, a number of tests of the LOFT and LOBI researches have been analyzed. Some results are reported in this paper. They clearly show a very promising behavior, although disagreement points suggest further improvements

Additional details

Additional titles

Subtitle (English)
A very fast-running code for the analysis of ST and SB-LOCA in PWRS

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
ISBN
0-89448-136-3
Imprint Title
Anticipated and abnormal transients in nuclear power plants
Imprint Pagination
vp.
Journal Page Range
p. XV-35-XV-43.

Conference

Title
Topical meeting on anticipated and abnormal transients in nuclear power plants.
Dates
12-15 Apr 1987.
Place
Atlanta, GA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22077643
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCIDENTS; COOLANTS; F CODES; LOSS OF COOLANT; MODIFICATIONS; PWR TYPE REACTORS; SPECIFICATIONS; STEAM GENERATORS; TRANSIENTS
Descriptors DEC
BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-870418--.