2007HAL (Le Centre pour la Communication Scientifique Directe)Open access

Neutronic Study of Slightly Modified Water Reactors and Application to Transition Scenarios

Richard Chambon, P. Guillemin, A. Nuttin, Adrien Bidaud, N. Capellán, S. David, O. Méplan, J. N. Wilson

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Key concepts: Fissile material, Nuclear engineering, Thorium, Plutonium, Thorium fuel cycle, Uranium-233, Environmental science, Nuclear reactor core

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