Open AccessUO2 and PuO2 utilization in high temperature engineering test reactor with helium coolant
Author(s) -
Abdul Waris,
Indarta Kuncoro Aji,
Novitrian,
Syeilendra Pramuditya,
Zaki Su’ud
Publication year - 2016
Publication title -
aip conference proceedings
Language(s) - English
Resource type - Conference proceedings
eISSN - 1551-7616
pISSN - 0094-243X
DOI - 10.1063/1.4943735
Subject(s) - nuclear engineering , coolant , criticality , mox fuel , helium , materials science , graphite , nuclear reactor , nuclear physics , plutonium , physics , atomic physics , engineering , composite material
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