Neutron flux distribution calculation for various spatial mesh of finite slab geometry using one-dimensional diffusion equation
Author(s) -
Mohammad Ali Shafii,
Winka Wino Yunanda,
Dian Fitriyani,
Syeilendra Pramuditya
Publication year - 2019
Publication title -
aip conference proceedings
Language(s) - English
Resource type - Conference proceedings
SCImago Journal Rank - 0.177
H-Index - 75
eISSN - 1551-7616
pISSN - 0094-243X
DOI - 10.1063/1.5135510
Subject(s) - neutron flux , neutron transport , physics , geometry , neutron , diffusion equation , diffusion , flux (metallurgy) , nuclear reactor core , mechanics , computational physics , materials science , mathematics , nuclear physics , thermodynamics , economy , metallurgy , economics , service (business)
Accelerating Research
Robert Robinson Avenue,
Oxford Science Park, Oxford
OX4 4GP, United Kingdom
Address
John Eccles HouseRobert Robinson Avenue,
Oxford Science Park, Oxford
OX4 4GP, United Kingdom