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Abstract

As part of the LWR safety programme of the JRC, several advanced thermalhydraulic system codes are being assessed at Ispra. The aim of this exercise is to check whether the codes can calculate, with sufficient accuracy, the phenomena occurring in loss of coolant accidents (LOCAs) in a power plant. The ability of procedures to mitigate the extent of the accident can then be evaluated. The work presented here refers to the German reactor safety code DRUFAN/ATHLET and the French reactor safety code CATHARE and has concentrated on the study of phenomena present in small break LOCAs. Both integral tests and supportive separate effect studies have been carried out. The separate studies were performed to investigate specific phenomena in order to check the codes' results against both separate effect tests and analytic solutions. The bulk of the work, however, has involved performing pre- and post-test predictions of a series of small break loss of coolant accidents performed in the JRC Ispra LOBI loop. In general it can be stated that the standard versions of both codes are capable of modelling and capturing the key physical phenomena present in small break LOCAs.

Additional information

Authors: DUFFIELD J S, JRC Ispra (IT);SHEPHERD I M, JRC Ispra (IT);FRIZ G, JRC Ispra (IT);EIFLER W, JRC Ispra (IT);NIJSING R, JRC Ispra (IT)
Bibliographic Reference: Paper presented: Seminar on the Commission Contribution to Reactor Safety Research, Congress Centre "Villa Ponti", Varese (IT), Nov. 20-24, 1989
Availability: Available from (1) as Paper EN 35063 ORA
Record Number: 199010030 / Last updated on: 1994-12-01
Category: PUBLICATION
Original language: en
Available languages: en
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