The effect of code user and boundary conditions on RELAP calculations of MTR research reactor transient scenarios

Author:

Khedr Ahmed1,Adorni Martina2,d’Auria Francesco2

Affiliation:

1. Atomic Energy Authority, National Center for Nuclear Safety Cairo, Egypt

2. DIMNP - University of Pisa, Pisa, Italy

Abstract

The safety evaluation of nuclear power and re search reactors is a very important step before their construction and during their operation. This evaluation based on the best estimate calculations requires qualified codes qualified users, and qualified nodalizations. The effect of code users on the RELAP5 results during the analysis of loss of flow transient in MTR research reactors is presented in this pa per. To clarify this effect, two nodalizations for research reactor different in the simulation of the open water surface boundary conditions of the reactor pool have been used. Very different results are obtained with few choices for code users. The core natural circulation flow with the be ginning of core boiling doesn't stop but in creases. The in creasing in the natural circulation flow shifts out the boiling from the core and the clad temperature decreases be low the local saturation temperature.

Publisher

National Library of Serbia

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

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