Design-Related Studies for the Preliminary Safety Assessment of the Molten Salt Fast Reactor
Author:
Affiliation:
1. Laboratoire de Physique Subatomique et de Cosmologie UJF, CNRS0IN2P3, Grenoble INP, 53, rue des Martyrs 38026 Grenoble Cedex, France
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE12-70
Reference8 articles.
1. Possible Configurations for the Thorium Molten Salt Reactor and Advantages of the Fast Nonmoderated Version
2. J.M. FLAUS, O. ADROT, and Q. D. NGO, “A First Step Toward a Model Driven Diagnosis Algorithm Design Methodology,” presented at Safety and Reliability for Managing Risk (ESREL 2011), Troyes, France, September 18–22, 2011.
3. X. DOLIGEZ, “Influence du retraitement physico-chimique du sel combustible sur le comportement du MSFR et sur le dimensionnement de son unité de retraitement,” PhD Thesis, Grenoble Institute of Technology, France (2010) (in French).
4. “MCNP4B—A General Monte Carlo N Particle Transport Code,” J. F. BRIESMEISTER, Ed. LA-12625-M, Los Alamos National Laboratory (1997).
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