Fission gas release during the SPX1-HCDA
Creators
- 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France)
Description
This paper analyses the fission gas release kinetics during the SPX1-Hypothetical Core Disruptive Accident (HCDA) from the stand point of the radiological and mechanical consequences. The SPX1-HCDA transient taken into account in this paper is a Loss of Flow (LOF) driven Transient Over Power accident (TOP). The beginning of equilibrium cycle (BOEC) and the end of equilibrium cycle (EOEC) were considered. For the steady state nominal power conditions a core chart of fission gas produced and released (inside the pin) was calculated with average and maximum burn up values. During the LOF phase, temperature and gas pressure evolutions occur within the clad; additionally during the TOP phase, fuel clad interaction and molten fuel clad contacts occur. (orig./RW)
Additional details
Publishing Information
- Publisher
- North-Holland.
- Imprint Place
- Amsterdam (Netherlands)
- ISBN
- 0444 86693 0
- Imprint Title
- Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. C
- Imprint Pagination
- 313 p.
- Journal Page Range
- p. 19-28.
Conference
- Title
- 7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7).
- Dates
- 22-26 Aug 1983.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 15053643
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; LOSS OF FLOW; REACTION KINETICS; REACTOR CORE DISRUPTION; SUPER PHENIX REACTOR; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; KINETICS; LIQUID METAL COOLED REACTORS; PLUTONIUM REACTORS; REACTOR ACCIDENTS; REACTORS; SODIUM COOLED REACTORS
Optional Information
- Secondary number(s)
- EUR--8596(Vol.C).