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ORNL-5011

MOLTEN-SALT REACTOR PROGRAM

SEMIANNUAL PROGRESS REPORT

For Period Ending August 31, 1974

INTRODUCTIONvii

SUMMARYix

PART 1. MSBR DESIGN, DEVELOPMENT, AND SAFETY

1. DESIGN AND SYSTEMS ANALYSIS2

1.1 ORNL Study of MSR Designs2

1.1.1 Plant and Equipment Studies2

1.1.2 Neutronic Analysis2

1.1.3 Xenon Behavior3

1.2 Tritium Behavior in Molten-Salt Systems3

1.2.1 Reactor Calculations3

1.2.2 Studies of Loop Experiments4

1.3 Molten-Salt Reactor Information System5

2. SYSTEMS AND COMPONENTS DEVELOPMENT6

2.1 Gaseous Fission Product Removal6

2.1.1 Bubble Generator6

2.1.2 Bubble Separator6

2.1.3 Bubble Formation and Coalescence Test6

2.1.4 Bubble Size Measurement7

2.1.5 Mass Transfer to Circulating Bubbles7

2.1.6 Bubble Generation Analysis8

2.2 Molten-Salt Steam Generator Industrial Program9

2.2.1 Resumption of the Conceptual Design Study9

2.2.2 Preliminary Results9

2.3 Gas Systems Technology Facility10

2.4 Coolant-Salt Technology Facility10

2.5 Forced Convection Loop (MSR-FCL-2 and 2b)14

2.5.1 Introduction14

2.5.2 Operation of MSR-FCL-2 with Fluoroborate14

2.5.3 Post Run Inspections14

2.5.4 Cleanup and Modifications15

2.5.5 Purging the System and Adding Salt15

2.5.6 Operation of MSR-FCL-2b with Fuel Salt16

3. REACTOR SAFETY18

3.1 Safety Events in MSBR18

3.2 MSBR Neutronic Excursions18

PART 2. CHEMISTRY

4. FUEL SALT CHEMISTRY22

4.1 The Chemistry of Tellurium in Molten Li2BeF422

4.2 Exposure of Metallurgical Samples to Tellurium Vapor22

4.3 Removal of Iodide from LiF-BeF2 Melts by HF-H2 Sparging:

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