Behaviour of CANDU Fueld During LOCA: ELOCA-A Predictions Versus Measurements at PBF

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E. Kohn
V.I. Nath
M. Tayal

Abstract

A large break loss-of-coolant accident (LOCA) in a CANDU nuclear reactor would result in a rapid increase of fuel and sheath temperatures. The temperature increase would, in turn, increase the gas pressure within the fuel and reduce the strength of the sheath material. Outside the fuel the loss of coolant from the primary heat transport system decreases pressure. The resulting pressure difference would cause deformation of the hot fuel sheath. Under certain circumstances, the deformation could be severe enough to fail the sheath thus releasing the fission products to the primary heat transport system. The computer code ELOCA-A is used to model the transient fuel behaviour following such an accident. ELOCA-A is a modified version of ELOCA.Mk 2 enabling us to consider the effects of axial variations in the microstructure of the sheath material caused by brazing of appendages to the sheath. The ELOCA-A code also features modelling of axial variations in neutron flux, pellet heat generation rate and heat transfer to the coolant. It predicts fuel pellet and sheath temperatures, sheath oxidation, sheath strain and probability of beryllium assisted cracking. A loss-of-coolant accident (LOCA) experiment was jointly sponsored by AECL and Ontario Hydro in the Power Burst Facility (PBF) at Idaho National Engineering Laboratories (INEL). This test was undertaken to provide an all-effects verification of the understanding of CANDU fuel behaviour during LOCA's. An extensive out-pile experimental program had provided single effects data which had been used for modelling such excursions. Integrated out-pile tests have confirmed our understanding of and accurate modelling of fuel under LOCA conditions. The integrated test in PBF provided the final proof that our understanding was complete and provided an experimental database for verification of transient fuel codes. The experiment was performed with modified CANDO fuel elements. The post-test measurements are compared with ELOCA-A predictions of strain. The agreement, considering the test modifications and assumptions, is excellent.

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