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ORNL-2626

MOLTEN-SALT REACTOR PROGRAM

QUARTERLY PROGRESS REPORT

For Period Ending October 31, 1958

SUMMARYiii

PART 1. REACTOR DESIGN STUDIES

1.1. CONCEPTUAL DESIGN STUDIES AND NUCLEAR CALCULATIONS3

Interim Design Reactor3

Fuel Fill-and-Drain System3

Fuel-to-Steam Heat Transfer3

Comparative Costs of Several Systems4

Experimental Reactor Calculations6

Nuclear Calculations6

Nuclear Characteristics of Homogeneous, Two-Region, Molten-Fluoride-Salt

Reactors Fueled with U2336

Blanket Fissions in the Reference Design Reactor9

Comparison of Ocusol and Compone Calculations10

Heterogeneous Reactors11

Gamma-Ray Heating Calculations11

1.2. COMPONENT DEVELOPMENT AND TESTING19

Fuel Pump Development19

Development Tests of Salt-Lubricated Bearings19

Development Tests of Conventional Bearings20

Mechanical Seals21

Radiation-Resistant Electric Motors for Use at High Temperatures22

Design Studies of Fuel Pumps22

Frozen-Lead Pump Seal23

Development of Techniques for Remote Maintenance of the Reactor System25

Mechanical Joint Development25

Evaluation of Expansion Joints for Molten-Salt Reactor Systems32

Remote Maintenance Demonstration Facility35

Heat Exchanger Development37

Al2Cl6 Thermal-Convection Loop37

Molten-Salt Heat Transfer Coefficient Measurement38

Design, Construction, and Operation of Materials Testing Loops39

Forced-Circulation Loops39

In-Pile Loops42

1.3. ENGINEERING RESEARCH44

Physical Property Measurements44

Enthalpy and Heat Capacity44

Surface Tension45

Apparatus Fabrication and Calibration46

Molten-Salt Heat-Transfer, Studies46

1.4. INSTRUMENTATION AND CONTROLS47

Resistance-Type Continuous Fuel Level Indicator47

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