![]() In the course of this review, it became apparent that the state of the properties database was strong in some areas and weak in others. 3 in order to evaluate the combined effects of various factors. Heat-transfer properties are considered as a group in Sect. Certain factors in this table, such as melting point, vapor pressure, and nuclear properties, can be viewed as stand-alone parameters for screening candidates. Table A presents a summary of the properties of the candidate coolant salts. The short-lived activation products, long-lived transmutation activity, and reactivity coefficients associated with various salt candidates were estimated using a computational model. The moderating ratio and neutron-absorption cross-section were compiled for each salt. Some simple screening factors related to the nuclear properties of salts were also developed. Key chemical factors that influence material compatibility were also analyzed for the purpose of more » screening salt candidates. The physical properties most relevant for coolant service were reviewed. This report provides an assessment of candidate salts proposed as the primary coolant for the AHTR based upon a review of physical properties, nuclear properties, and chemical factors. For applications at temperatures greater than 900 C the AHTR is also referred to as a Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR). The Advanced High-Temperature Reactor (AHTR) is a novel reactor design that utilizes the graphite-matrix high-temperature fuel of helium-cooled reactors, but provides cooling with a high-temperature fluoride salt. ![]() These alternative coolants are considered in this report. However, alternative coolant salts (i.e., chlorides and fluoroborates) that were not considered in the previous report should be considered for service in the heat-transfer loop. Some of the more » fluoride salts identified in the previous study are also appropriate for consideration as the secondary coolant in a heat-transfer loop therefore, results from the previous report are used in this document. Salts that are suitable for use as the primary coolant in a high-temperature nuclear reactor were previously analyzed. A preliminary assessment of the cost of the raw materials required to produce the coolant is also presented. The physical properties most relevant for coolant service were reviewed, and key chemical factors that influence material compatibility were also analyzed for the purpose of screening candidate salts. This report provides an assessment of candidate salts proposed as the coolant for the loop that shuttles heat from the Next Generation Nuclear Plant (NGNP) to the Nuclear Hydrogen Initiative (NHI) hydrogen-production plant.
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