Standardized test facilities were developed and operate for investigating the compatibility of structural materials and flowing molten fluoride salts. The standard loop accommodates various combinations of materials, fluid, flow, rates, and temperature differentials and permits fabrication of components in sufficient quantity for cost reduction. The test loop consists of a pump, two heated sections, a cooled section, a drain tank, and a frozen-plug-type valve. Automatic controls and equipment were developed to prevent solidification of the salt mixtures (mp, 800 to 1100 un. Concent 85% F) in the event of a loss of power. Most test loops were fabricated of 0.5-in.-OD, 0.045-in.-wall tubing, and operate with a temperature differential of up t...
A preliminary study of molten salt pcwer reactors was made. The most promising fuel carrier salts we...
The feasibility of the containment of a molten sodium fluoride- zirconium fluoride salt at 550 deg C...
Molten salts are considered within the Very High Temperature Reactor program as heat transfer media ...
This report develops a proposal to design and construct a forced convection test loop. A detailed te...
84-88Hydrogen (H2) is an alternative to petroleum based environment polluting transport fuel. High t...
Two fused chloride salt eutectics, binary LiCl-KCl and ternary NaCl- KCl- MgCl/sub 2/, were used in ...
Molten salt is an effective coolant for a wide range of applications, including nuclear reactors, co...
Corrosion screening tests were carried out on potential materials of construction for use in a fused...
Abstract. Experimental studies have been developed on a new freeze plug concept for safety valves in...
Nuclear power is experiencing a strong renewed interest, being identified as the only source of ener...
Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, of...
AbstractSandia National Laboratories has recently completed the design, construction, commissioning,...
Corrosion is an electrochemical process resulting in deterioration of metals working in reactive env...
Technologie solných reaktorů je známá již od druhé poloviny čtyřicátých let minulého století. Několi...
This report was prepared to identify the source documentation used to evaluate the drain tanks in th...
A preliminary study of molten salt pcwer reactors was made. The most promising fuel carrier salts we...
The feasibility of the containment of a molten sodium fluoride- zirconium fluoride salt at 550 deg C...
Molten salts are considered within the Very High Temperature Reactor program as heat transfer media ...
This report develops a proposal to design and construct a forced convection test loop. A detailed te...
84-88Hydrogen (H2) is an alternative to petroleum based environment polluting transport fuel. High t...
Two fused chloride salt eutectics, binary LiCl-KCl and ternary NaCl- KCl- MgCl/sub 2/, were used in ...
Molten salt is an effective coolant for a wide range of applications, including nuclear reactors, co...
Corrosion screening tests were carried out on potential materials of construction for use in a fused...
Abstract. Experimental studies have been developed on a new freeze plug concept for safety valves in...
Nuclear power is experiencing a strong renewed interest, being identified as the only source of ener...
Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, of...
AbstractSandia National Laboratories has recently completed the design, construction, commissioning,...
Corrosion is an electrochemical process resulting in deterioration of metals working in reactive env...
Technologie solných reaktorů je známá již od druhé poloviny čtyřicátých let minulého století. Několi...
This report was prepared to identify the source documentation used to evaluate the drain tanks in th...
A preliminary study of molten salt pcwer reactors was made. The most promising fuel carrier salts we...
The feasibility of the containment of a molten sodium fluoride- zirconium fluoride salt at 550 deg C...
Molten salts are considered within the Very High Temperature Reactor program as heat transfer media ...