Published 1982
| Version v1
Book
Design of the future 1500 MW fast reactor pit and analysis of the behaviour of the different solutions to accidental loadings
Description
After recalling the design of the reactor pit based on that of Creys Malville, the present document describes a new design where the safety vessel is anchored in the reactor pit concrete. The behaviours of the safety vessel and of the pit under accidental situations such as leakage of primary sodium are thoroughly examined, pinpointing the main differences liable to affect the safety requirements. The preliminary studies conducted since 1980 as well as the future prospects are presented in this document
Additional details
Additional titles
- Original title (no language)
- Actes de la conference de Lyon.
Publishing Information
- Publisher
- SFEN.
- Imprint Place
- Paris (France)
- Imprint Title
- Proceedings of the L.M.F.B.R. safety topical meeting
- Imprint Pagination
- 651 p.
- Journal Page Range
- v. 4 p. 179-187.
Conference
- Title
- L.M.F.B.R. safety topical meeting.
- Dates
- 19-23 Jul 1982.
- Place
- Lyon (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 14787445
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DYNAMIC LOADS; FEASIBILITY STUDIES; LEAKS; LMFBR TYPE REACTORS; MATERIALS; REACTOR VESSELS; SAFETY ANALYSIS; SODIUM; SPECIFICATIONS; SUPPORTS
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; CONTAINERS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MECHANICAL STRUCTURES; METALS; REACTORS
Optional Information
- Notes
- Imprint:Actes de la conference de Lyon.;Vol. 4.