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Abstract

The results of a non-linear sensitivity analysis performed on the predictions made by the Primary Containment code SEURBNUK/EURDYN concerning a typical pool-type Liquid Metal Fast Breeder Reactor undergoing a Core Disruptive Accident, are presented and discussed. The sensitivity of the computed responses representing the roof loading and vessel deformation processes have been determined, considering the effects of variations imposed on six input parameters considered as the most relevant. The hierarchy of these parameters in producing response variations has been assessed. In general, the responses have shown a limited sensitivity and a non- linear behaviour to the prescribed parameter variations.

Additional information

Authors: BENUZZI A, JRC-ISPRA;YERKESS A, JRC-ISPRA;MERLINI S JRC-ISPRA, JRC-ISPRA
Bibliographic Reference: CONFERENCE ON FAST REACTOR SAFETY, GUERNSEY, CHANNEL ISLANDS/GB, MAY 11-16 1986, AVAILABILITY: CEC-LUXEMBOURG, DG-XIII/A2, BP 1907, MENTIONING PAPER ORA 32603 E
Availability: Can be ordered online
Record Number: 1989126094900 / Last updated on: 1989-05-01
Category: PUBLICATION
Available languages: en