Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-Battery™) using MCNP4C

The neutron transport code, Monte Carlo N-Particle (MCNP) which was wellkown as the gold standard in predicting nuclear reaction was used to model the small nuclear reactor core called »U-battery™», which was develop by the University of Manchester and Delft Institute of Technology. The paper introd...

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Bibliographic Details
Main Author: Pauzi, A.M.
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Published: 2018
Online Access:http://dspace.uniten.edu.my/jspui/handle/123456789/7932
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