The study about the transient characteristics of metallic fuel sodium cooled fast reactor in the unprotected loss of flow accident based on the SAS4A code
Description
Unprotected loss of flow accident (ULOF) is the most typical severe accident in sodium cooled fast reactor, which is focused by scholars civil and abroad. Metallic fuel has different safety characteristics with the oxide fuel as the important development direction of future sodium fast reactor, accident analysis of which is also a research focus at home and abroad. This paper bases on one Cooperation Research Project proposed by ANL and organized by IAEA, analyses the Shut-down Removal Test-45R of the metallic fuel sodium cooled fast reactor EBR-II in the US with SAS4A code, to research the transient characteristics of it in ULOF accident. Studies have shown that, metallic fuel sodium cooled fast reactor has very good inherent safety performance, which can reduce the reactor power in ULOF accident through the negative feedback itself. (author)
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49086000.pdf
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Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers
- Imprint Pagination
- vp.
- Journal Page Range
- 18 p.
- Report number
- IAEA-CN--245
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49086000
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANL; COMPUTER CODES; COORDINATED RESEARCH PROGRAMS; EBR-2 REACTOR; IAEA; LOSS OF FLOW; REACTOR KINETICS; REACTOR SAFETY; SAFETY ANALYSIS; SEVERE ACCIDENTS; URANIUM; URANIUM OXIDES
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ACTINIDES; BEYOND-DESIGN-BASIS ACCIDENTS; BREEDER REACTORS; CHALCOGENIDES; ELEMENTS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; INTERNATIONAL ORGANIZATIONS; KINETICS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; METALS; NATIONAL ORGANIZATIONS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH PROGRAMS; SAFETY; SODIUM COOLED REACTORS; URANIUM COMPOUNDS; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Notes
- 8 refs., 12 figs., 5 tabs.
- Secondary number(s)
- IAEA-CN--245-011