Guidelines of elevated temperature structural design methods to realize compact reactor vessels
- 1. University of Tokyo, Tokyo (Japan)
- 2. Japan Atomic Energy Agency (JAEA), Ibaraki (Japan)
- 3. Mitsubishi FBR Systems, Inc.(MFBR), Tokyo (Japan)
Description
Main loadings of reactor vessels in fast reactor plants are thermal stresses induced by fluid temperature change at transient operation. Structures respond to them with elastic plastic creep deformation under high temperature conditions. It can induce incremental deformation and creep fatigue crack at critical portions around the sodium surface, thermal stratification layer and core support structures. Those phenomena are so complex that design evaluation becomes sometimes too conservative. In order to achieve precise high temperature design for realizing compact reactor vessels of fast reactor plants, next guidelines were proposed for thermal load modeling, structural analysis and strength evaluation. This paper gives the summary of these guidelines. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-104114-2
- Imprint Title
- Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). COMPANION CD-ROM. Proceedings of an International Conference
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 10 p.
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios
- Acronym
- FR13
- Dates
- 4-7 Mar 2013
- Place
- Paris (France)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46091072
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; CREEP; DEFORMATION; FAST REACTORS; FATIGUE; OPERATION; REACTOR VESSELS; RECOMMENDATIONS; SIMULATION; SODIUM; SUPPORTS; THERMAL STRESSES
- Descriptors DEC
- ALKALI METALS; CONTAINERS; ELEMENTS; EPITHERMAL REACTORS; MECHANICAL PROPERTIES; MECHANICAL STRUCTURES; METALS; REACTORS; STRESSES
Optional Information
- Notes
- 14 figs., 14 refs.
- Secondary number(s)
- IAEA-CN--199/362