Piramid, a loop for European PAHR irradiations according to a Mol integrated device
- 1. Centre d'Etude de l'Energie Nucleaire, Mol (Belgium)
- 2. Commission of the European Communities, Ispra (Italy). Joint Research Centre
Description
On behalf of the Commission of the European Communities, the Nuclear Research Centre of Mol, S.C.K./C.E.N., is in charge of the execution in the BR2 reactor of three in-pile experiments aiming at the study of the post-accident heat removal (PAHR) phenomenology. The purpose of these experiments is to validate the physical models and the computer codes used to predict the temperature fields in a sodium saturated bed and in debris retention devices. From the large experience gained with in-pile Na-loops, the S.C.K./C.E.N. has followed the approach of an integrated design, which presents numerous advantages. The paper describes the lay-out of the first experiment, PIRAMID 1, which is foreseen for temperatures up to 1400 deg C in an UO2 debris bed with a bed loading of 1000 kg UO2/m2. It emphasizes also the importance of the back-up programme related to the in-pile PAHR programme. (Auth.)
Additional details
Publishing Information
- Publisher
- D. Reidel.
- Imprint Place
- Dordrecht (Netherlands)
- ISBN
- 90-277-1568-8
- Imprint Title
- Irradiation technology
- Imprint Pagination
- 759 p.
- Journal Page Range
- p. 739-748.
Conference
- Title
- International Topical Meeting on Irradiation Technology.
- Dates
- 28-30 Sep 1982.
- Place
- Grenoble (France).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 15028735
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BR-2 REACTOR; EXPERIMENTAL DATA; FISSION PRODUCTS; FUEL-COOLANT INTERACTIONS; IN PILE LOOPS; MELTDOWN; SIMULATION; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; IRRADIATION REACTORS; ISOTOPES; MATERIALS; MATERIALS TESTING REACTORS; NUMERICAL DATA; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 diagrams; 2 figs. Imprint:Includes index and list of participants.