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Abstract

At PSI, modelling the behaviour of fuel and cladding under RIA conditions (Reactivity Initiated Accident) can be performed with the codes FREY (from EPRI) and TRANSURANUS (from ITU). A comparison of the codes was done by calculating the behaviour of a UO2 fuel rod during a 1.75 $ RIA with both codes. RIA was assumed in a PWR at hot zero power with an average rod burnup of 47.7 GWd/tU. The resulting peak enthalpy rise in this moderately loaded rod was deltaHmax = 51 cal/g (Hmax = 70 cal/g). The fuel centre temperatures calculated with FREY were 40-50°C higher than those given by TRANSURANUS. Differences were also found in the calculated fuel axial elongation, fuel radial expansion, and stresses in the cladding. Finally, the capability of the present versions of FREY and TRANSURANUS to deal with high burnup issues is discussed and possible improvements for modelling high burnup rods are listed.

Additional information

Authors: HELLWIG Ch, Paul Scherrer Institut, Villigen (CH);WALLIN H, Paul Scherrer Institut, Villigen (CH);LASSMANN K, European Commission, Joint Research Centre, Institute for Transuranium Elements, Karlsruhe (DE)
Bibliographic Reference: An oral report given at: Fuel Safety Research Specialists Meeting Organised by: Japan Atomic Energy Research Institute (JAERI) Held at: Tokai-mura (JP), 4-5 March 2002
Record Number: 200214571 / Last updated on: 2002-04-04
Category: PUBLICATION
Original language: en
Available languages: en
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