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

• Main Author: Pauzi A.M.
• Other Authors: 55812611200
• Format: Conference paper
• Published: Institute of Physics Publishing 2023
• Subjects: Computer software; Criticality (nuclear fission); Reactor cores; Small nuclear reactors; Cladding material; Core configuration; Gold standards; Graphite matrix; High temperature nuclear reactors; Monte carlo n particles; Neutron transport; University of Manchester; conference proceeding; data set; high temperature; model validation; nuclear power plant; numerical model; software; standard (reference); High temperature reactors

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...