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Abstract

For the SNR300 prototype fast reactor, a numerical simulation of the loading of the primary containment undergoing an Hypothetical Core Disruptive Accident (HCDA) with a mechanical release of 370MJ had to be analysed using a wellproven fluid dynamics/structural code. The code SEURBNUK2 has been adequately validated using data from many experimental scaledmodel tests, and analytic solutions. In parallel to the SEURBNUK development, the coupled code SEURBNUKEURDYN release 1 has also evolved. The finite element code EURDYNO1 is a substitute for the builtin thin shell finite difference scheme available in SEURBNUK and it allows for better modelling of thick structures and structural interconnectivity. Since SEURBNUK2 and SEURBNUK/EURDYN were at the same level of development, both codes were used in the SNR300 analysis and their structural responses compared.

Additional information

Authors: YERKESS A JRC ISPRA ESTAB. (ITALY) MEIER E S GESELLSCHAFT FUER REAKTORSICHERHEIT (GRS), KOELN (GERMANY) , JRC ISPRA ESTAB. (ITALY);GESELLSCHAFT FUER REAKTORSICHERHEIT (GRS), KOELN (GERMANY)
Bibliographic Reference: 9TH SMIRT INTERNATIONAL CONFERENCE LAUSANNE (SWITZERLAND), AUG. 17-21, 1987 WRITE TOL CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 33375 ORA
Availability: Can be ordered online
Record Number: 1989126007000 / Last updated on: 1988-02-01
Category: PUBLICATION
Available languages: en