Dimensional behavior of the experimental gas-cooled reactor fuel element at elevated temperatures
U.S. Atomic Energy Commission, 1961 - Science - 50 pages
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adjacent pellets apparatus Atomic axial elongation axial expansion Capsule During Thermal central temperature central U0p temperature central UO CIRCUMFERENTIAL RIDGE CLADDING AND FUEL cladding collapsed cladding temperature cooling rates deformation diametral gap dilatometer dimensional behavior dished EGCR fuel element elevated temperatures elongation per cycle expansion characteristics EXTENSOMETER external pressure fission products fracture characteristics fuel and cladding fuel body fuel capsule fuel pellet HEATING RATE irradiation experiments isothermal J. A. L. Robertson J. R. Weir macrocracks measured Metallurgy nearly a function number of thermal ORNL oxide pellet and cladding Pellet Interface permanent axial plastic strain predicted pressure differential radial gap existed Radial Thermal Gradients radiographic techniques shown in Fig Simulated EGCR Fuel sintering solid pellet stainless steel strain per cycle thermal conditions thermal cycling Thermal Expansion top pellet total surface area tubing U0p pellets UNCLASSIFIED ORNL-LR-DWG UO temperature upper temperature limit Uranium Oxide