Instability evaluation of steam generator in a large scale sodium test facility of fast reactors. Modification of BOST code
Creators
- 1. Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
Instability analysis was carried out using BOST code for a steam generator in a large scale sodium test facility of fast reactors. However, it was found that BOST code gave stable characteristics under the conditions of higher pressure in water-steam system than MONJU conditions, even if the flow ratio of sodium to water was increased as expected to give unstable condition. Here, modification of BOST code was considered and we found some points to be modified. However, main reasons of stable calculation were not resolved. In this report, the current status of BOST code was summarized especially for the stable calculation under the higher pressure condition for further modification and a new code based on current knowledge and coding technique. (author)
Availability note (English)
Available from INIS in electronic formFiles
31009725.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 66 p.
- Report number
- JNC-TN--9410-99-004
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31009725
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALGORITHMS; B CODES; HYDRAULICS; INSTABILITY; LMFBR TYPE REACTORS; PRESSURE DEPENDENCE; PROGRAMMING; REACTOR COOLING SYSTEMS; STEAM GENERATORS; THERMODYNAMICS
- Descriptors DEC
- BOILERS; BREEDER REACTORS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MATHEMATICAL LOGIC; REACTOR COMPONENTS; REACTORS; VAPOR GENERATORS