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13.2 Reductive Extraction of Rare Earths from Molten Mixtures of

LiF, BeF2, and ThF4 into Bismuth and Bismuth Alloy Mixtures176

13.2.1 Effect of Salt Composition176

13.2.2 Effect of Metal-Phase Composition178

13.3 Protactinium Studies in the High-Alpha Molten-Salt Laboratory180

13.3.1 Tests Dealing with the Possibility of Thorium Carbide Formation181

13.3.2 Tests Dealing with the Possibility of Oxide Contamination181

13.3.3 Experiment with Molybdenum Container184

13.3.4 Conclusions185

14. DEVELOPMENT AND EVALUATION OF ANALYTICAL METHODS FOR

MOLTEN-SALT REACTORS186

14.1 Determination of Oxide in MSRE Salts186

14.2 Determination of Uranium (III) in Radioactive MSRE Fuel by a

Hydrogen-Reduction Method188

14.3 Determination of Total Reducing Power of Radioactive MSRE Salts189

14.4 Disproportionation of Electrochemically Generated U(V)

in LiF-BeF2 ZrF4 at 500°C190

14.5 Exchange Current Measurements on the Nickel-Nickel(II) Couple in Molten Fluorides191

14.6 Voltammetric Studies of Chromium(II) in Molten LiF-BeF2-ZrF4 at 500°C192

14.7 Development of a Molten-Salt Spectrophotometric Facility for Hot-Cell Use192

14.8 Spectra of U(V) and U(VI) Species in Molten Fluoride Salts193

14.9 Absorption Spectra of Several 3d Transition Metal Ions in Molten Fluoride Solution194

14.10 Simultaneous Electrochemical and Spectrophotometric Study

of Solutes in Molten Fluoride Salts195

14.11 Development of a Gas Chromatograph for Analysis of the MSRE Blanket Gas195

14.12 Analysis of MSRE Helium for Hydrocarbons196

14.13 Measurement by Ge(Li) Gamma Spectroscopy of Fission Products Deposited in

Components of the MSRE196

14.14 In-Pile Fission-Product Penetration in MSRE and Pyrolytic Graphite197

14.15 Precision Analysis of 235U by Delayed-Neutron Counting198

14.16 High-Precision Polarographic Determination of Uranium198

14.17 A Precise Determination of Uranium in MSRE Fuel198

PART 4. MOLTEN-SALT IRRADIATION EXPERIMENTS

15. MOLTEN-SALT CONVECTION LOOP IN THE ORR200

15.1 Studies of Surface Wetting of Graphite by Molten Salt200

16. GAMMA IRRADIATION OF FLUOROBORATE203

16.1 Gamma Dose Rates and Decay of Spent Fuel Elements203

16.2 Second Fluoroborate Irradiation Experiment203

16.3 Estimated Neutron Effects205

17. EXAMINATION OF MSRE OFF-GAS JUMPER LINE206

17.1 Chemical Analysis207

17.2 Radiochemical Analysis207

17.3 Discussion208

PART 5. MATERIALS DEVELOPMENT

18. MSRE SURVEILLANCE PROGRAM211

18.1 MSRE Surveillance Specimens211

18.1.1 Examinations of Specimens Removed213

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