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Preparation and Handling of Salt Mixtures for the Molten Salt Reactor Experiment.

J.H. Shaffer
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In this paper, the authors propose a method to solve the problem of "uniformity" and "uncertainty" in the context of health care, and propose a solution.
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Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR)

D.F. Williams
TL;DR: In this article, the authors presented an assessment of candidate salts proposed as the primary coolant for the Advanced High-Temperature Reactor (AHTR) based upon a review of physical properties, nuclear properties, and chemical factors.
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Corrosion in the molten fluoride and chloride salts and materials development for nuclear applications

TL;DR: In this paper, a comprehensive approach covering all relevant work in the field of corrosion data accumulated since the 1950s to date, major corrosion problems and corresponding mechanisms, metallurgical factors, historical development of corrosion resistant alloys and recent attempts are also reviewed.
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Status of Preconceptual Design of the Advanced High-Temperature Reactor (AHTR)

TL;DR: The Advanced High-Temperature Reactor (AHTR) concept is a collaboration of Oak Ridge National Laboratory, Sandia National Laboratories, and the University of California at Berkeley.
Journal ArticleDOI

Molten salt actinide recycler and transforming system without and with Th–U support: Fuel cycle flexibility and key material properties

TL;DR: In this article, the feasibility of MOlten Salt Actinide Recycler and Transforming (MOSART) system without and with U-Th support fuelled with different compositions of transuranic elements (TRU) trifluorides from spent LWR fuel.
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Aggregation and data analysis of corrosion studies in molten chloride and fluoride salts

TL;DR: In this article, the authors surveyed corrosion studies in molten fluoride and chloride salts and aggregated key data into a single dataset, and found that salt purity had the strongest correlation with corrosion rates in molten chlorides and fluorides.
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