3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code
Author:
Funder
Institut Teknologi Bandung
Publisher
Elsevier BV
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1. Preface for the ”OUTCOMES AND ACHIEVEMENTS FROM RESEARCHES ORIENTING THE FUTURE IN NUCLEAR FISSION TECHNOLOGY: Asia South-East (Vietnam, Thailand, Indonesia, Malaysia, Singapore, Bangladesh) and Australia”;Nuclear Engineering and Design;2024-11
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