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ORNL-5047

MOLTEN-SALT REACTOR PROGRAM

SEMIANNUAL PROGRESS REPORT

For Period Ending February 28, 1975

Introductionvii

SUMMARYix

PART 1. MSBR DESIGN, DEVELOPMENT, AND SAFETY

1. DESIGN AND SYSTEMS ANALYSIS3

1.1 Tritium Behavior in Molten-Salt Systems3

1.1.1 MSBR Tritium Studies3

1.1.2 Coolant Salt Technology Facility Calculations11

1.2 Neutronic Analyses14

1.3 High-Temperature Design15

1.3.1 Analytical Investigation of the Applicability of Simplified Ratchetting and

Creep-Fatigue Rules to Reactor System Component Geometries15

1.3.2 Inelastic Analyses of MSR Piping Subjected to Internal Pressure and

Transient Temperature Cycles21

2. SYSTEMS AND COMPONENTS DEVELOPMENT23

2.1 Molten-Salt Steam Generator Industrial Program23

2.2 Gas-Systems Technology Facility23

2.2.1 General23

2.2.2 Mark II Pump24

2.2.3 Densitometer25

2.3 Coolant-Salt Technology Facility25

2.4 Forced-Convection Loops29

2.4.1 Operation of MSR-FCL-2b29

2.4.2 MSR FCL-3 and FCL431

3. SAFETY STUDIES32

3.1 Salt-Spill Accidents32

3.1.1 Potential Causes32

3.1.2 Direct Consequences34

3.1.3 Deferred Consequences35

PART 2. CHEMISTRY

4. FUEL-SALT CHEMISTRY37

4.1 Tellurium Deposition on Hastelloy N Surfaces in an MSBR37

4.2 Exposure of Metallurgical Samples to Tellurium Vapor40

4.3 Effect of Oxygen on the UF3/UF4 Equilibrium in Molten Fluoride Solutions41

4.4 The Uranium Tetrafuoride-Hydrogen Equilibrium in Molten Fluoride Solutions43

4.5 Porous-Electrode Studies44

5. COOLANT-SALT CHEMISTRY47

5.1 Chemistry of Sodium Fluoroborate47

5.2 Corrosion of Structural Alloys by Fluoroborates49

5.2.1 Thermodynamics of Cr(III) in Fluoroborate49

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