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Abstract

The paper presents the post-test analysis of the LOFW/ATWS experiment L9-3 on LOFT apparatus, performed using RELAP-4, MOD-6 and ALMOD-JRC computer codes. Attention is given to the ability of RELAP 4 to simulate an ATWS accident: in this connection parametric studies about modelling of core, pressurizer and secondary side of the steam generator are described. The computed results are analyzed, comparing them with the experimental data and with the ones calculated using ALMOD-JRC, a code especially developed (by GRS and JRC) for the simulation of transients and including specific physical models relating to ATWS phenomena. This code is exploited to the upmost of its ability and it is analyzed how the presence of heat storage into the structure and different nodalization of the core affect the result.

Additional information

Authors: ANDREANI M, UNIVERSITY OF PISA (ITALY);JRC ISPRA ESTAB. (ITALY);MAZZINI M, UNIVERSITY OF PISA (ITALY);JRC ISPRA ESTAB. (ITALY);ORIOLO F, UNIVERSITY OF PISA (ITALY);JRC ISPRA ESTAB. (ITALY);CACCIABUE P C UNIVERSITY OF PISA (ITALY), UNIVERSITY OF PISA (ITALY);JRC ISPRA ESTAB. (ITALY);JRC ISPRA ESTAB. (ITALY), UNIVERSITY OF PISA (ITALY);JRC ISPRA ESTAB. (ITALY)
Bibliographic Reference: INTERNATIONAL MEETING ON THERMAL REACTOR SAFETY, KARLSRUHE (GERMANY), SEPT. 10-13, 1984 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31843 ORA
Availability: Can be ordered online
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