Published May 1982
| Version v1
Journal article
Dynamic analysis of the condensate feedwater system in boiling water reactor plants
Creators
- 1. Hitachi Energy Research Laboratory, Hitachi, Ltd. 1168 Moriyama-cho, Hitachi-shi, Ibaraki-ken 316
Description
The computer code, CONFAC, has been developed for dynamic analysis of the condensate feedwater system in boiling water reactor plants. This code simulates the hydrodynamics in the piping system, the pump dynamics, and the feedwater controller in order to clarify the system transient characteristics in such cases as pump trip incidents. Code verification was performed by comparison between analytical results and actual plant operational data. Satisfactory agreement was obtained. With the code, appropriate pump start/stop interlocks were estimated for preventing pump cavitation in pump trip incidents
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 57
- Journal Issue
- 2
- Series
- Nucl. Technol.
- Journal Page Range
- 163-174
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15072945
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCURACY; BWR TYPE REACTORS; C CODES; CAVITATION; COMPUTERIZED SIMULATION; CONDENSATES; FEEDWATER; FLOW REGULATORS; FLUID-STRUCTURE INTERACTIONS; HYDRODYNAMICS; NUCLEAR POWER PLANTS; PIPES; PUMPS; REACTOR COOLING SYSTEMS; SYSTEMS ANALYSIS; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; CONTROL EQUIPMENT; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID MECHANICS; HYDROGEN COMPOUNDS; MECHANICS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS