Assessing the benefit of thorium fuel in a once through molten salt reactor-Reference-Cited by-同舟云学术

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Assessing the benefit of thorium fuel in a once through molten salt reactor

Published:2024-11 Issue: Volume:176 Page:105369
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Dwijayanto R Andika Putra^ORCID,Miftasani Fitria,Harto Andang Widi

Publisher

Elsevier BV

Reference38 articles.

1. Neutronics calculations for denatured molten salt reactors: assessing resource requirements and proliferation-risk attributes;Ahmad;Ann. Nucl. Energy,2015

2. Fuel cycle modelling of open cycle thorium-fuelled nuclear energy systems;Ashley;Ann. Nucl. Energy,2014

3. Design and performance features of a single-fluid molten-salt breeder reactor;Bettis;Nucl. Appl. Technol.,1970

4. Sustainable thorium nuclear fuel cycles: a comparison of intermediate and fast neutron spectrum systems;Brown;Nucl. Eng. Des.,2015

5. Integral molten salt reactor neutron physics study using Monte Carlo N-particle code;Carter;Nucl. Eng. Des.,2020

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