Proposal on the mitigation methods of thermal stress near the sodium
Creators
- 1. Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan). Tokai Works
Description
A Reactor vessel of fast rector plants contains high temperature liquid sodium in its inside and its upper end is supported by a low temperature structures. Therefore, a significant temperature gradient will arise at the vessel wall near the sodium surface. For this reason, a large thermal stress will be generated around this part. To lower this stress and to protect the vessel, a number of methods have been applied the plants. Generally, these mitigation methods by protection equipments for thermal stress also have some problems such as, increase a mount of materials or to be complicate for control, hard to maintenance and so on. In this research, authors suggested another simple methods for thermal stress, and evaluated their effects using computer analysis. The results obtained in this research are as follows. Authors suggested one method, circulate high temperature gas around outside of the vessel and evaluated the effects of this method by analysis. In case of using this method, Sn (one of index values of design) value might be getting lower about 45%. Authors also suggested another method by setting up a heat transfer plate outside of the vessel and evaluated the effects of this method by analysis. Effects of this method depend on material of the plate. In case of using Carbon as material of plate, Sn value might be 27% lower and in case of using 12Cr steel as material of plate, Sn value might be 15% lower. Authors also suggested another method by changing material of the guard vessel to be the one which has good ability of heat transfer and evaluated the effects of this method by analysis. In case of changing material of guard vessel to 12Cr steel, Sn value might be lower about 12%. (author)
Availability note (English)
Available from JICST Library (JICST: Japan Science and Technology Corporation, Information Center for Science and Technology), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-4781 (domestic), FAX: +81-3-3979-2210 (oversea)Additional details
Publishing Information
- Imprint Pagination
- 49 p.
- Report number
- JNC-TN--9400-2003-094
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 35080502
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- CARBON; CIRCULATING SYSTEMS; FINITE ELEMENT METHOD; HEAT TRANSFER; LMFBR TYPE REACTORS; NUMERICAL ANALYSIS; PLATES; REACTOR VESSELS; STEEL-CR12; STRESS RELAXATION; TEMPERATURE DISTRIBUTION; THERMAL STRESSES
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CALCULATION METHODS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CONTAINERS; CORROSION RESISTANT ALLOYS; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MARTENSITIC STEELS; MATERIALS; MATHEMATICAL SOLUTIONS; MATHEMATICS; NONMETALS; NUMERICAL SOLUTION; REACTORS; RELAXATION; STAINLESS STEELS; STEELS; STRESSES; TRANSITION ELEMENT ALLOYS