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ORNL-4676

MOLTEN-SALT REACTOR PROGRAM

SEMIANNUAL PROGRESS REPORT

For Period Ending February 28, 1971

INTRODUCTIONix

SUMMARYxi

PART 1. MOLTEN-SALT REACTOR EXPERIMENT

1. POSTOPERATION EXAMINATIONS1

1.1 Outline of Program1

1.2 Reactor Vessel and Core2

1.3 Fuel Pump6

1.4 Heat Exchanger11

1.5 Leak at Freeze Valve FV-10512

1.6 Other Examinations12

1.7 Evaluation of Tools and Procedures13

2. FURTHER INVESTIGATIONS17

2.1 Test of Coolant Salt Flowmeter and Conclusions17

2.2 Inventories of Residual Uranium and Plutonium18

2.3 Search for Unrecovered 235U20

PART 2. MSBR DESIGN AND DEVELOPMENT

3. DESIGN21

3.1 Single-Fluid 1000-MWe MSBR Design Study Report21

3.2 Molten-Salt Demonstration Reactor Design Study22

3.2.1 Introduction22

3.2.2 Addition of Third Salt-Circulation Loop22

3.2.3 Salt Overflow and Gas Stripping Systems24

3.2.4 Primary Drain Tank24

3.2.5 Drain Valves for Salt Service25

3.2.6 Heat Exchangers25

3.2.7 Building and Containment28

3.3 Initial Temperature Transients in Empty MSBR "Reference Design" MSBR Heat Exchangers32

3.4 The Consequences of Tubing Failure in the MSBR Heat Exchanger34

3.5 Tritium Distribution and Control in the MSBR35

3.6 Industrial Study of 1000-MWe Molten-Salt Breeder Reactor36

3.7 MSBE Design36

3.7.1 General36

3.7.2 MSBE Core Design36

3.7.3 MSBE Primary Heat Exchanger Design39

4. REACTOR PHYSICS41

4.1 Physics Analysis of MSBR41

4.1.1 Single-Fluid MSBR Reference Design41

4.1.2 Fixed-Moderator Molten-Salt Reactor43

4.2 MSR Experimental Physics45

4.2.1 HTLTR Lattice Experiments45

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