NEUTRONIC STUDY OF HTGR (High Temperatue Gas-Cooled) NUCLEAR REACTOR USING THORIUM NUCLEAR FUEL (Th-U233)O2 and (Th-U233)N

The development of design in nuclear reactor is aimed to make nuclear reactor capable to produce energy with the best safety feature. HTGR nuclear reactor (High Temperature Gas-Cooled Reactor) is one of nuclear reactor in Generation IV. Beside the development of reactor’s design, research in deve...

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Bibliographic Details
Main Author: AZZAHWA (NIM : 10212019), SARAH
Format: Final Project
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/24213
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Institution: Institut Teknologi Bandung
Language: Indonesia

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