PUBLIC SERVICE COMPANY OF COLORADO 330-MW(E) HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending December 31, 1968. Page: 7 of 261
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CONTENTS
INTRODUCTION .......................................................... i
Part I
TASK I. COMPONENT DEVELOPMENT .......................................... 1
Reactor Vessel ...................................................... 1
Prestressing System ........................................... 1
Concrete Properties .............................................. 1
Thermal Barrier ..................................................... 1
Attachment Fixtures for Class A Thermal Barrier ............... 3
Instrumentation and Electrical ...................................... 19
Core Outlet Gas Thermometers .................................... 19
Auxiliary Equipment and Special Tools ............................. 19
Reserve Shutdown System .......................................... 27
Orificing Mechanism .............................................. 27
TASK II. NUCLEAR ANALYSIS .............................................. 28
Fuel Cycle Analysis ................................................. 28
Status of Nuclear Design ...................................... 28
Cross-section Evaluation for Reference Design 7 ............... 28
Fuel Zoning and Power Shaping ...................................... 33
Loading Distribution .......................................... 33
Depletion Analysis .............................................. 35
Reactivity Effects in the Initial Core (Reference Design 7) ... 38
Calculational Methods ........................................... 39
Analytical Studies .................................................. 41
Fuel Particle Loading ......................................... 41
Burnable Poison Rod Heating ..................................... 42
Boron Concentration in Control Rods ............................. 43
TASK III. FUEL DEVELOPMENT ............................................ 45
Fuel Element Design .............................................. 45
Mechanical Design ............................................. 45
Thermal and Coolant Flow Design ................................. 46
Fission-product Transport ....................................... 48
Materials ........................................................ 49
Particle Fuel Systems ......................................... 51
Graphite Development .......................................... 52
Control Material .............................................. 62
Irradiation Testing ........................................... 71
Helium Purification System ....................................... 92
Sorbent Beds ..................................................... 92
TASK IV. FUEL ELEMENT PROOF TESTING .................................... 98
Part II
TASK I. FUEL TRANSFER MACHINE ........................................ 101t1ii
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PUBLIC SERVICE COMPANY OF COLORADO 330-MW(E) HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending December 31, 1968., report, January 1, 1969; San Diego, California. (https://digital.library.unt.edu/ark:/67531/metadc864169/m1/7/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.