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Mohamad Ali Shafii
Jurusan Fisika FMIPA Universitas Andalas Padang
Control & Systems Engineering Mathematics

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Solution methods of neutron transport equation in nuclear reactors Mohamad Ali Shafii
Jurnal ILMU DASAR Vol 14 No 2 (2013)
Publisher : Fakultas Matematika dan Ilmu Pengetahuan Alam Universitas Jember

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (530.187 KB) | DOI: 10.19184/jid.v14i2.320

Abstract

A few numerical methods that usually used to solve neutron transport equation in nuclear reactor are SN dan PN method, Monte Carlo, Collision Probability and Methods of Characteristics . First two methods have been developed using diffusion approach, and last three methods suitable are applicated for transport approximation. Those of three methods have important role in the desain of nuclear reactors. In addition to follow the development of advanced reactor designs, the three methods were chosen because they do not use diffusion approach these are more accurate methods, as well as less need considerable computer memory. Of all the existing methods, the CP method has several advantages among the others. Keywords : Neutron transport, SN, PN, CP, MOC, MC
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