Three-dimension thermal hydraulic studies for the pool-type fast reactor of CEFR
Creators
- 1. China Inst. of Atomic Energy, Beijing (China)
Description
With the development of the computer software and hardware, 3-dimension numerical analysis technology has become an important part of the reactor core and plenums design and research of the fast reactor, sometimes even plays an un-replacable role in the design. In this paper, the typical thermal-hydraulic phenomena in the pool-type fast reactor are analysed by using 3-dimension numerical analysis codes and programs. It can be said that it will play an important role in the thermal hydraulic design and research by using these tools. And at the same time, it will also set good examples and speed up the application of these technologies by summing up these experiences and methods in order that it can be used in the future design and analyses for the large-scaled pool-type fast reactor. (authors)
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 29
- Journal Issue
- 4
- Journal Page Range
- p. 308-315
- ISSN
- 0258-0918
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 41120445
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPUTER CODES; COMPUTERS; DESIGN; FAST REACTORS; NUMERICAL ANALYSIS; POOL TYPE REACTORS; REACTOR CORES; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- EPITHERMAL REACTORS; FLUID MECHANICS; HYDRAULICS; MATHEMATICS; MECHANICS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 figs., 4 refs.