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Abstract

The first approach in determining the best surface temperature for the Phebus-FP vessel was to run computer codes such as JERICHO and CONTAIN that are used for calculating the consequences of an accident in a full-sized reactor. The results of these calculations demonstrated a sensitivity to heat and mass transfer correlations. The codes have not been validated in geometries similar to the Phebus vessel so a priori there were few grounds for preferring one correlation to another. It was therefore decided to perform a series of thermalhydraulic tests in the containment beforehand in order to calibrate the codes. Blind pre-test calculations were performed with the codes JERICHO, MELCOR, CONTAIN, CONTEMPT and CONT; the results are compared with the thermalhydraulic experiments and analysed to find the reasons for the discrepancies in the code results. Armed with the knowledge of these tests, another benchmark exercise was organised with boundary conditions corresponding to measured values from the experiments. Codes using the well-mixed hypothesis as well as multi-compartment and three dimensional codes were used. Comparing the results of the calculations with measurements contributed to further understanding of the thermalhydraulic behaviour of the Phebus-FP vessel and a better understanding of the uncertainties of the codes.

Additional information

Authors: SHEPHERD I, JRC Ispra (IT);HONTANON E, Borsista CCR;GAILLOT S, CEA Cadarache (FR);HERRANZ L, CIEMAT, Madrid (ES);AKAGANE K, NUPEC, Tokyo (JP)
Bibliographic Reference: Paper presented: Heat and mass transfer in severe reactor accidents, Cesme (TR), May 21-26, 1995
Availability: Available from (1) as Paper EN 38977 ORA
Record Number: 199510710 / Last updated on: 1995-07-07
Category: PUBLICATION
Original language: en
Available languages: en
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