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ORNL-2799

MOLTEN-SALT REACTOR PROGRAM

QUARTERLY PROGRESS REPORT

For Period Ending July 31, 1959

SUMMARYiii

PART 1. REACTOR DESIGN STUDIES

1.1. NUCLEAR CALCULATIONS AND DESIGN STUDIES3

Nuclear Performance of a Two-Region, Graphite-Moderated, Molten-Salt Breeder Reactor3

1.2. COMPONENT DEVELOPMENT AND TESTING15

Molten-Salt-Lubricated Bearings for Fuel Pumps15

Hydrodynamic Journal Bearings15

Hydrodynamic Thrust Bearings18

Test of Pump Equipped with One Molten-Salt-Lubricated Journal Bearing18

Bearing Mountings19

Self-Welding of INOR-819

Mechanical Seals for Pumps19

Pump Endurance Testing19

Remote Maintenance Demonstration Facility20

Frozen-Lead Pump Seal30

Mechanical Joints for the Reactor System30

Design, Construction, and Operation of Materials-Testing Loops31

Forced-Circulation Corrosion Loops31

In-Pile Loops31

1.3. ENGINEERING RESEARCH34

Physical-Property Measurements34

Viscosity34

Enthalpy and Heat Capacity37

Thermal Expansion39

Heat-Transfer Studies39

1.4. INSTRUMENTS AND CONTROLS43

Molten-Salt-Fuel Level Indicators43

PART 2. MATERIALS STUDIES

2.1. METALLURGY47

Dynamic Corrosion Studies47

INOR-8 Thermal-Convection Loops47

Inconel Thermal-Convection Loops50

INOR-8 Forced-Circulation Loops55

General Corrosion Studies59

Carburization Tests on Inconel and INOR-8 in Systems

Containing Fuel 130 and Graphite59

Sodium-Graphite Carburization Tests60

Penetration of Graphite by Molten Fluorides61

Removal of Oxide Contaminants from Graphite62

Mechanical Properties of INOR-863

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