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