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ORNL-2723

MOLTEN-SALT REACTOR PROJECT

QUARTERLY PROGRESS REPORT

For Period Ending April 30, 1959

SUMMARYvi

PART 1. REACTOR DESIGN STUDIES

1.1. NUCLEAR CALCULATIONS AND DESIGN STUDIES3

Nuclear Calculations3

Effect of Ion-Exchange Processing of Rare-Earth Fission

Products on Performance of Interim Design Reactor Fueled with U2333

Nuclear Performance of a One-Region, Graphite-Moderated,

Unreflected, Thorium-Conversion, Molten-Salt-Fueled Reactor3

Initial Nuclear Performance of One-Region, Graphite-Moderated,

Graphite-Reflected, Thorium-Conversion, Molten-Salt-Fueled Reactors9

Nuclear Performance of Two-Region, Graphite-Moderated,

Molten-Salt-Fueled, Breeder Reactor10

Effects of Fast Neutron Reactions in 9Be on Reactivity of Molten-Salt Reactors14

Oracle Code MSPR-Cornpone 02020

Design of 30-MWe Experimental Reactor21

Fuel Drain System22

Gamma Heating in the Core Vessel of the 30-MWe Experimental Reactor22

1.2. COMPONENT DEVELOPMENT AND TESTING24

Salt-Lubricated Bearings for Fuel Pumps24

Hydrodynamic Journal Bearings24

Hydrodynamic Thrust Bearings25

Test of Pump Equipped with One Salt-Lubricated Journal Bearing25

Bearing Mountings25

Mechanical Seals for Pumps27

Pump Endurance Testing27

Frozen-Lead Pump Seal27

Techniques for Remote Maintenance of the Reactor System28

Design, Construction, and Operation of Materials Testing Loops32

Forced-Circulation Loops32

In-Pile Loops35

1.3. ENGINEERING RESEARCH37

Physical Property Measurements37

Enthalpy and Heat Capacity37

Viscosity39

Surface Tension39

Heat-Transfer Studies41

Hydrodynamic Studies44

1.4. INSTRUMENTS AND CONTROLS47

Molten-Salt-Fuel Level Indicators47

INOR-8 High-Temperature Pressure Transmitters47

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