Reliability of double-wall-tube steam generator for FBR considering water leak accident frequency
- 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab
Description
For early realization, a fast breeder reactor (FBR) is required to reduce construction cost. A reactor concept in which the intermediate heat transport system is eliminated by introducing a double-wall-tube steam generator is one convincing approach. The reliability of the double-wall-tube SG in a water leak accident (sodium-water reaction accident) due to tube failure is strongly related to the mitigating system design. The safety design of the double-wall-tube SG approach is investigated to limit the accident occurrence below 10-7 (1/ry. A tube-to-tube weld is excluded from the reference design, because the welding process is too difficult and complicated to effectively prevent adhesion of the double-wall-tube. The reliability of the tube-to-tube plate was evaluated at 10-10 (l/hr) for an inner tube and 10-9 (l/hr) for an outer with reference to the failure experience of previous SGs. The failure must be detected within 30 to 60 minutes. (author)
Additional details
Publishing Information
- Journal Title
- Denryoku Chuo Kenkyusho Hokoku
- Journal Issue
- no.T99092
- Journal Page Range
- p. 1-4, 1-18
- ISSN
- 1340-4652
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 32025679
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FAILURES; FBR TYPE REACTORS; FEEDWATER; LEAKS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; STEAM GENERATORS; TUBES; WELDED JOINTS
- Descriptors DEC
- BOILERS; BREEDER REACTORS; COOLING SYSTEMS; ENERGY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; HYDROGEN COMPOUNDS; JOINTS; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTORS; SAFETY; VAPOR GENERATORS; WATER