IPSN proposal for high burnup fuel LOCA experimental programs
Creators
- 1. Institut de Protection et de Surete Nucleaire, Departement de Recherches en Securite, Cadarache (France)
Description
Safety studies performed in IPSN and elsewhere pointed out that high burn up might induce significant effects, especially those related with fuel relocation during LOCA situations. Uncertainties exist regarding how much the existing safety margins associated with peak clad temperature, clad oxidation, core coolability, clad residual ductility can be reduced by new fuels like the MOX one, burn up increases, the arrival of various alloys for fuel rod cladding. A better knowledge of specific phenomena associated to fuel effects is required in order to estimate the new margins and to resolve the pending uncertainties related to the LOCA criteria. Therefore, in addition to the programmes currently planned in the Halden reactor, IPSN is preparing the so-called 'APRP-Irradie' (High Burn up fuel LOCA) programme. One of the important aspects of this programme is In-Pile experiments involving bundle geometries in the PHEBUS facility located at Cadarache, France. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- Fuel behaviour under transient and LOCA conditions. Proceedings of a technical committee meeting
- Imprint Pagination
- 298 p.
- Journal Page Range
- p. 279-289
- Report number
- IAEA-TECDOC-CD--1320
Conference
- Title
- Technical committee meeting on fuel behaviour under transient and LOCA conditions
- Dates
- 10-14 Sep 2001
- Place
- Halden (Norway)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 34014779
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CLADDING; DUCTILITY; EXPERIMENT PLANNING; HBWR REACTOR; LOSS OF COOLANT; MIXED OXIDE FUELS; OXIDATION; PHEBUS FACILITY; SAFETY STANDARDS; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ACCIDENTS; BHWR TYPE REACTORS; CHEMICAL REACTIONS; DEPOSITION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FUELS; PLANNING; POWER REACTORS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID FUELS; STANDARDS; SURFACE COATING; TANK TYPE REACTORS; TENSILE PROPERTIES; THERMAL REACTORS
Optional Information
- Notes
- 16 refs, 8 figs Imprint:Data in PDF format; Acrobat Reader for Windows 3.01, 4.0 and 5.0 included