Published April 2008
| Version v1
Journal article
Designing outlet nozzle in main vessel of supercritical water reactor
Creators
- 1. Key laboratory of Condition Monitoring and Control for Power Plant Equipment of Ministry of Education, North China Electric Power University, Beijing (China)
- 2. China Inst. of Atomic Energy, Beijing (China)
Description
The numerical analysis was performed on temperature distribution of the outlet nozzles in main vessel of SCWR (supercritical water reactor) by using computational fluid dynamics software CFX. The thermal sleeve between the outlet nozzle and the main vessel was designed to avoid direct connection between them. Thus the temperature gradient of the main vessel closed to the outlet nozzle was decreased, and the safety of the reactor was enhanced. The result shows that the geometrical parameters, such as the diameter and the length of the thermal sleeve, have a definite influence on the temperature gradient of the thermal sleeve connected with the outlet nozzle. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 42
- Journal Issue
- 4
- Journal Page Range
- p. 325-328
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 40076803
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; CONTAINERS; DESIGN; FLUID MECHANICS; JOINTS; LENGTH; NOZZLES; NUMERICAL ANALYSIS; SAFETY; SLEEVES; SUPERCRITICAL STATE; TEMPERATURE DISTRIBUTION; TEMPERATURE GRADIENTS; WATER; WATER COOLED REACTORS
- Descriptors DEC
- COMPUTER CODES; DIMENSIONS; HYDROGEN COMPOUNDS; MATHEMATICS; MECHANICS; OXYGEN COMPOUNDS; REACTORS; SIMULATION
Optional Information
- Notes
- 5 figs., 4 refs.