Community Research and Development Information Service - CORDIS

Abstract

This paper describes how a reactor safety nuclear computer program can be modified and improved with the aim of reaching a very fast running tool to be used as a physical model in a plant simulator, without penalizing the accuracy of results. It also discusses some ideas on how the physical theoretical model can be combined to a driving statistical tool for the build up of the entire package of software to be implemented in the simulator for risk and reliability analysis. The approach to the problem, although applied to a specific computer program, can be considered quite general if an already existing and well tested code is being used for the purpose. The computer program considered is ALMOD, originally developed for the analysis of the thermohydraulic and neutronic behaviour of the reactor core, primary circuit and steam generator during operational and special transients.

Additional information

Authors: CACCIABUE P C JRC ISPRA ESTAB. (ITALY) TOZZI A MATEC, MILANO (ITALY) , JRC ISPRA ESTAB. (ITALY); MATEC, MILANO (ITALY)
Bibliographic Reference: INTERNATIONAL CONFERENCE ON SIMULATION FOR NUCLEAR TECHNOLOGY, CAMBRIDGE (UK), APRIL 9-11, 1984 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31231 ORA
Availability: Can be ordered online
Record Number: 1989122072400 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en