Open AccessPower and neutron flux distribution analysis in the RSG-GAS reactor :preliminary study to identify the reactor readiness as Power Ramp Test Facility (PRTF)
Author(s) -
Octaviana Erawati Fadli,
Suparmi Suparmi,
Azizul Khakim,
Suharyana Suharyana,
Riyatun Riyatun
Publication year - 2019
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/1153/1/012111
Subject(s) - neutron flux , nuclear engineering , neutron temperature , neutron , research reactor , neutron poison , nuclear physics , neutron cross section , flux (metallurgy) , nuclear reactor , materials science , neutron source , nuclear reactor core , physics , engineering , metallurgy