Published 1981
| Version v1
Book
Study in the Phebus reactor of fuel behaviour during a LOCA
Creators
- 1. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service des Elements Combustibles et Structures
- 2. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Service d'Essais de Surete
- 3. CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Surete Nucleaire
Description
The fuel behaviour upon LOCA conditions is studied in an in-pile loop, in Phebus reactor. This paper presents: a short description of Phebus reactor; the current program (adjusting the thermohydraulic conditions is order to get cladding failure); the program developments (consequences involved by cladding failure); the fuel test conditions determination
Additional details
Additional titles
- Original title (French)
- Etude dans le reacteur Phebus du comportement du combustible lors d'un accident de perte de refrigerant
Publishing Information
- Publisher
- OECD.
- Imprint Place
- Paris, France
- ISBN
- 92-64-02234-1
- Imprint Title
- Proceedings of a CSNI specialist meeting on safety aspects of fuel behaviour in off-normal and accident conditions, Espoo, Finland, 1 - 4 September 1980
- Imprint Pagination
- 658 p.
- Journal Page Range
- p. 455-470.
Conference
- Title
- CSNI specialist meeting on safety aspects of fuel behaviour in off-normal and accident conditions.
- Dates
- 1 - 4 Sep 1980.
- Place
- Espoo, Finland.
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 13689300
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL RODS; IN PILE LOOPS; LOSS OF COOLANT; PWR TYPE REACTORS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS