Published February 2003
| Version v1
Journal article
18-months fuel cycles stretch-out operation verification of protection against primary overpressure
Description
A whole range of primary temperature and pressurizer level is studied during stretch-out operation. The CATIA2 code is used to analyze a loss of main steam flow accident. The results demonstrate that primary overpressure does not cause any limitation to stretch-out operation. The pressurizer level program and average temperature are suitable for operation diagram. The bounding stretch out operation diagram is given in the present document. Two representative cases are chosen to explain these analyses
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 24
- Journal Issue
- 1
- Journal Page Range
- p. 73-76
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 34053660
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- C CODES; DAYA BAY-1 REACTOR; DAYA BAY-2 REACTOR; FRACTURING; FUEL MANAGEMENT; NUCLEAR POWER PLANTS; PRESSURE DEPENDENCE; PRESSURE RELEASE; PRESSURE SUPPRESSION; PRESSURIZERS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; STEAM LINES; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MANAGEMENT; NUCLEAR FACILITIES; NUCLEAR MATERIALS MANAGEMENT; PIPELINES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS