Thermo-mechanical response of LMFBR fuel elements using EAC with emphasis on the TRANSURANUS module
Creators
- 1. Commission of the European Communities, Ispra (Italy). Joint Research Centre
- 2. Commission of the European Communities, Karlsruhe (Germany, F.R.). Gemeinsame Forschungsstelle - Europaeisches Inst. fuer Transurane
Description
The European Accident Code EAC is a multichannel modular computer code for simulating the initiation phase of low-probability whole-core accidents in LMFBRs, i.e. loss of flow (LOF) or transient overpower (TOP) events. The code presents itself as an informatic structure into which various stand-alone modules from the Joint Research Centre and from other laboratories have been included. Three phenomena mainly control the neutronic behaviour of the whole core, namely fuel pin behaviour, sodium thermohydraulics and fuel motion. Fuel behaviour, in particular, is computed by means of the TRANSURANUS program which is an advanced tool for fuel performance analysis, extensively used in both the LWR and the LMFBR areas. Because of the modular structure of EAC, the computation of these interacting phenomena proceeds necessarily in a sequential manner, not only channel-wise but also time-wise. The purpose of this paper is to illustrate how the EAC approach remedies the usual drawbacks of a weak coupling, in particular as far as the strong interaction between fuel pin and coolant channel is concerned. Numerical results will be presented on the basis of an international benchmark exercise dedicated to a hypothetical LOF accident in the irradiated core of the fictitious 700 MWe EUROPE reactor. (orig.)
Additional details
Publishing Information
- Publisher
- Balkema.
- Imprint Place
- Rotterdam (Netherlands)
- ISBN
- 90-6191-764-6
- Imprint Title
- Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. C
- Imprint Pagination
- 187 p.
- Journal Page Range
- p. 159-164.
Conference
- Title
- 9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19028876
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BOILING; BOUNDARY CONDITIONS; DIFFERENTIAL EQUATIONS; E CODES; FLOWSHEETS; FUEL-COOLANT INTERACTIONS; LMFBR TYPE REACTORS; LOSS OF FLOW; PROBABILITY; SODIUM; T CODES; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BREEDER REACTORS; COMPUTER CODES; DIAGRAMS; ELEMENTS; EPITHERMAL REACTORS; EQUATIONS; FAST REACTORS; FBR TYPE REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; METALS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTORS