Main factors of thermal fatigue failure induced by thermal striping and total simulation of thermal hydraulic and structural behaviors (research report)
Creators
- 1. Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
At incomplete mixing area of high temperature and low temperature fluids near the surface of structures, temperature fluctuation of fluid gives thermal fatigue damage to wall structures. This phenomenon is called thermal striping, which becomes sometimes a critical problem in LMFR plants. Since thermal striping phenomenon is characterized by the complex thermohydraulic and thermomechanical coupled problem, conventional evaluation procedures require mock-up experiments. In order to replace them by simulation-base methods, the authors have developed numerical simulation codes and applied them to analyze a tee junction of the PHENIX secondary circuit due to thermal striping phenomenon, in the framework of the IAEA coordinated research program (CRP). Through this analysis, thermohydraulic and thermomechanical mechanism of thermal striping phenomenon was clarified, and main factors on structural integrity was extracted in each stage of thermal striping phenomenon. Furthermore, simulation base evaluation methods were proposed taking above factors of structural integrity into account. Finally, R and D problems were investigated for future development of design evaluation methods. (author)
Availability note (English)
Available from INIS in electronic formFiles
31009711.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 38 p.
- Report number
- JNC-TN--9400-99-018
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31009711
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; COORDINATED RESEARCH PROGRAMS; FLUCTUATIONS; MIXING; PHENIX REACTOR; SECONDARY COOLANT CIRCUITS; SODIUM; STAINLESS STEEL-304; STRESS ANALYSIS; TEMPERATURE RANGE 0400-1000 K; THERMAL CYCLING
- Descriptors DEC
- ALKALI METALS; ALLOYS; AUSTENITIC STEELS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; 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; LMFBR TYPE REACTORS; MATERIALS; METALS; NICKEL ALLOYS; PLUTONIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH PROGRAMS; SIMULATION; SODIUM COOLED REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS; VARIATIONS