Published June 1992
| Version v1
Journal article
Accident management for a loss of feedwater in a pressurized water reactor
Creators
- 1. Univ. di Pisa, Dept. di Costruzioni Meccaniche e Nucleari, Via Diotisalvi, 2, I-56100 Pisa (Italy)
Description
In this paper a pressurized water reactor plant scenario is evaluated during a loss of feedwater following multiple failures and operator interventions. For a more realistic analysis, an experiment performed on the SPES facility is taken as a reference. A suitably qualified RELAP5/MOD2 code nodalization was used to evaluate the behavior of the facility under the failure of various systems and the activation of typical accident management recovery procedures
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 98
- Journal Issue
- 3
- Journal Page Range
- p. 277-288.
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24019608
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- FAILURE MODE ANALYSIS; FEEDWATER; LOSS OF COOLANT; M CODES; NUCLEAR FACILITIES; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR OPERATORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; PERSONNEL; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS