Published June 1993 | Version v1
Report

Precalculations for the bundle for the first Phebus-FP test FPT0

  • 1. Commission of the European Communities, Ispra (Italy). Joint Research Centre
  • 2. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France). Inst. de Protection et de Surete Nucleaire

Description

Phebus-FB is a 1:5000 scale facility where a series of six experiments will be carried out that aim to model the release, retention and chemical behaviour of fission products during a severe accident in a light water thermal reactor. The core, coolant circuit and containment are all modelled and the heating power to the bundle is supplied by nuclear fission in the fuel rods. In this paper we consider calculations that have been performed by different organisations, and with different computer codes, in preparation for the first test FPT-0. In particular we study the phenomena in the bundle. Here we are primarily concerned with thermalhydraulics, core degradation and fission product release. All of these are considered. We note that predictions for the temperature field in the bundle depend less on the code used than on the conductivity assumed for the surrounding shroud. Unlike a reactor the Phebus bundle will be hottest in the mid-plane. There will be three phases in the experiment. First a heat-up with considerable heat-generation from zircalloy oxidation and then, once the zircalloy is mostly consumed, a slower heat-up till the melting point of fuel is reached. The third phase is the cool-down. Because of the high degree of clad oxidation, little interaction between zircalloy and uranium dioxide is expected. Modelling of fission product release and transport is crude. Release is expected to be slow because the fuel in this first test is fresh but correlations used to model it can be expected to over-predict because they are based on irradiated fuel. We have so far made no calculations of transport, nucleation and deposition of fission products and aerosols in the core. (author). 15 refs, 28 figs, 1 tab

Part of:
Behaviour of core materials and fission product release in accident conditions in LWRs

Additional details

Publishing Information

Imprint Title
Behaviour of core materials and fission product release in accident conditions in LWRs
Imprint Pagination
259 p.
Journal Page Range
p. 251-257.
Report number
IAEA-TECDOC--706

Conference

Title
Technical committee meeting on behaviour of core materials and fission product release in accident conditions in LWRs.
Dates
16-19 Mar 1992.
Place
Aix-en-Provence (France).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
24067392
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTER CODES; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL-CLADDING INTERACTIONS; HYDRAULICS; PHEBUS REACTOR; REACTOR ACCIDENTS; TEMPERATURE DISTRIBUTION; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; POOL TYPE REACTORS; RADIOACTIVE MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; WATER MODERATED REACTORS

Optional Information