Affiliation:
1. National Center for Nuclear Safety, 3 Ahmed Alzomer Street, P.O. Box 7551, Nasr City, Cairo, Egypt, Email:
Abstract
Abstract
A detailed three-dimensional MCNP model of the ETRR-2 research reactor has been developed for the analysis of the neutronic parameters of the reactor. The model was used to determine the partial control plates reactivity worth and the behavior of the worth with time. The results of the present model were compared with the experimental measurements for partial control plates reactivity worth and with the design calculations for control plates behavior with time. The comparisons indicate satisfactory agreement.
Subject
Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation
Reference8 articles.
1. Neutronic Calculation to the TRIGA Ipr-R1 Reactor Using the WIMSD4 and CITATION Code;Annals of Nuclear Energy,2002
2. Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code;Kerntechnik,2004
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