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--.