Published May 2014
| Version v1
Journal article
Analysis of the impact on CCMS L VSL due to distribution of the temperature in the core
Creators
- 1. CNNC Hunan Taohuajiang Nuclear Power Company Ltd, Yiyang (China)
- 2. China Nuclear Power Engineering Company Ltd, Shenzhen (China)
Description
The impact on Reactor vessel level monitoring of CCMS due to uneven distribution of the core temperature in CPR1000 nuclear power plant is analyzed, the result shows that the uncertainty induced by the physical phenomenon, with the reactor coolant pumps keep in service, can be ignored. The impact on operator actions in SOP due to over-estimated reactor vessel level under total loss of feed water accident is also analyzed, the conclusion shows this over-estimation will not affect safety actions to be implemented in SOP. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Electronics and Detection Technology
- Journal Volume
- 34
- Journal Issue
- 5
- Journal Page Range
- p. 636-639
- ISSN
- 0258-0934
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 49079707
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCIDENTS; COOLANTS; COOLING; DISTRIBUTION; ERRORS; LOSSES; MONITORING; NUCLEAR POWER; NUCLEAR POWER PLANTS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR CORES; REACTOR VESSELS; SAFETY
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.