MSR_Awards

URL	Lead University	Funding Amount	Project Description
Reduction, Mitigation, and Disposal Strategies for the Graphite Wast of High Temperature Reactors	State University of New York, Stony Brook	$3,000,000	This project intends to develop economically attractive and environmentally sound irradiated graphite waste management strategies resulting in specific and significant cost savings for advanced nuclear systems.
Bridging the gap between experiments and modeling to improve the design of molten salt reactors	University of California, Berkeley	$2,998,545	The scope of this project is to improve our understanding of the role of impurities and fission products on the operational performance of MSRs as well as potential impact on accident scenarios.
Integrated Effects of Irradiation and Flibe Salt on Fuel Pebble and Structural Graphite Materials for Molten Salt Reactors	Massachusetts Institure of Technology		This project will investigate the irradiation response of the Flibe/fuel pebble carbon matrix and Flibe/structural graphite systems with a focus on salt infiltration and its effect on microstructure for molten salt reactor applications.
A Molten Salt Community Framework for Predictive Modeling of Critical Characteristics	Pennsylvania State University	$400,000	This research aims to develop a molten salt community framework to address the needs in advanced fuel cycles, including understanding salts via new theory of liquids, predicting salt characteristics via simulations,optimizing inversely molten salts, and
Understanding the Interfacial Structure of the Molten Chloride Salts by in-situ Electrocapillarity and Resonant Soft X-ray Scattering (RSoXS)	Pennsylvania State University	$400,000	The objective of the proposed research is to investigate the interplay between the interfacial structure of the molten salts and their electrochemical corrosion properties in Molten Salt Reactors (MSRs).
Nuclear Material Accountancy During Disposal and Reprocessing Molten Salt Reactor Fuel Salts	Texas A&M University	$399,997	The objective of this work is to develop and validate a method for measuring and predicting hold-up to eliminate operational risks and expenses during disposal of salt-wetted MSR components.
Optical Basicity Determination of Molten Fluoride Salts and its Influence on Structural Material Corrosion	University of Wisdonsin-Madison	$400,000	The proposed research is aimed at developing ion probes to determine the optical basicity of molten fluoride salts and studying its influence on structural material corrosion.
Los Alamos National Laboratory to lead study of molten-salt nuclear reactor materials		$9,250,000	LANL has been selected by the DOE as the lead on a $9.25 million, five-year collaborative project in nuclear energy research. The SciDAC program aims to advance modeling the behavior and properties of structural materials under molten salt conditions by u

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