X hits on this document

Word document

MOLTEN-SALT REACTOR PROGRAM - page 39 / 122

316 views

0 shares

0 downloads

0 comments

39 / 122

5. RADIATION CHEMISTRY OF THE MSRE SYSTEM79

Experiment ORNL-MTR-47-3:

Examination of INOR-8,Molybdenum, and Pyrolytic-Carbon Specimens79

Postirradiation Examination of Assembly ORNL-MTR-47-481

Nonvolatile Constituents in Graphite82

Metallographic Examination of the Graphite85

Implications of Uranium Deposition for the MSRE85

Postirradiation Examination of Assembly ORNL-MTR-47-586

Fluorine Evolution from Capsules 3 and 4 During Reactor Shutdowns86

Analysis of Gas from Sealed Capsules87

Visual and Photographic Examination of Capsules91

Preliminary Examination of the Fuel97

Neutron-Flux Determinations98

Plans for In-Pile Experiment ORNL-MTR-47-698

Gamma Irradiation of a Simulated MSRE Fuel Salt in the Solid Phase101

Experimental101

Discussion104

Fluorine Evolution from Solid Fluoride Salts Under Irradiation by VanDeGraaff Electrons105

Experimental105

Results106

Discussion108

Effect of Soft X-Rays on Solid Fluorides110

6. CHEMISTRY114

Phase Equilibrium and Solubility Studies Among Fluorides114

The System LiF-BeF2-ZrF4114

Crystallization of the MSRE Fuel117

Solubility of Uranium Trifluoride in a Reduced MSRE Fuel-Salt Mixture117

Stability of Uranium Trifluoride in Molten Fluoride Solvents119

Crystal Structure of 6LiF-BeF2-ZrF4120

Core and Blanket Fluids for Future Reactors123

Chlorides as Fast Reactor Fuels123

Fluoride Salts for Use as Blanket Fluids: The System NaF-KF-ThF4125

Phase Separation of Molten Halides and Lead126

Removal of Moisture from MSR Graphite127

Interfacial Behavior of Fluorides with Graphite and Metals132

Graphite132

Metals135

HF-H2O Equilibria with Molten Fluorides137

Removal of Sulfates from 2LiF-BeF2141

Fluoride Salt Production146

Production Process147

Raw-Material Procurement149

LiF Densification149

Development and Evaluation of Methods for the Analysis of the MSRE Fuel151

Electrochemical Analyses151

Oxidation States – Uranium153

Methods Development154

Mockup of Hot Cell155

7. FUEL PROCESSING161

Document info
Document views316
Page views316
Page last viewedFri Dec 09 22:02:28 UTC 2016
Pages122
Paragraphs5226
Words27095

Comments