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MOLTEN-SALT REACTOR PROGRAM - page 30 / 122

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Graphite Studies96

Evaluation of Grade TS-281 Graphite96

Effects of Thermal Decomposition Products of NH4F-HF on Graphite-INOR-8 Systems97

Fabrication of Gd2O3 and Gd2O3-Al2O3 Pellets98

5. IN-PILE TESTS100

ORNL-MTR-47 Molten-Salt Irradiation Experiments100

Experiment ORNL-MTR-47-4100

Experiment ORNL-MTR-47-5102

Post-Irradiation Examination of Experimental Assembly ORNL-MTR-47-3105

Chemical Analyses of Irradiated Fuel for Corrosion Products105

Distribution of Radioactivity and Salt in Irradiated Graphite106

Post-Irradiation Examination of Experimental Assembly ORNL-MTR-47-4106

Description of Capsule108

Fabrication and Loading of Capsules108

Fuel109

Graphite109

Decay Energy110

Irradiation and Temperature Data110

Production of Xenon and Krypton110

Gas Analyses112

Discussion of Results115

6. CHEMISTRY117

Phase Equilibrium Studies117

The System LiF-BeF2-ZrF4117

The System LiF-BeF2-ZrF4-ThF4-UF4118

LiF-UF4 Eutectic as a Concentrated Solution of UF4 for Fuel Makeup119

Fractionation of LiF-BeF2-ZrF4-ThF4-UF4 on Freezing121

Crystal Chemistry121

Oxide Behavior in Molten Fluorides -Dehydration of LiF122

Physical Properties of Molten Salts123

Density of LiF-BeF2-ZrF4-UF4123

Estimation of Densities of Molten Fluorides123

Graphite Compatibility125

Removal of Oxide from Graphite Moderator Elements125

Behavior of CF4 in Molten Fluorides128

Analytical Chemistry130

Determination of Oxygen in MSRE Fuel Mixtures130

Determination of Oxygen in Graphite131

Homogenization of Radioactive MSRE Fuel Samples131

7. FUEL PROCESSING133

8. ENGINEERING RESEARCH ON THERMOPHYSICAL PROPERTIES OF SALT MIXTURES135

Enthalpy135

Viscosity136

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