Gas-Cooled Reactor Project Semiannual Progress Report: September 1963 Page: VII
xxxiii, 462 p. : ill. ; 28 cm.View a full description of this report.
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vii
8. INVESTIGATIONS OF MODERATOR MATERIALS ........................ 227
Mechanical Properties of Graphite ............................ 227
In-Pile Creep of Graphite .................................... 227
Geometry Studies of Irradiation-Induced Changes in
Graphite .............................................. 232
Design Criteria for Graphite Components ...................... 240
Stress Analysis of Graphite Beam for In-Pile Creep Tests ..... 245
Transport of Gases Through Graphite .......................... 249
Oxidation of Graphite by Low Concentrations of Oxidants
in Helium ................................................... 254
Compatibility of Graphite and Metals in Hydrogen ............. 259
Graphite-Oxidation and Mass-Transfer Tests in a Low-
Pressure Loop ............................................... 260
Graphite-Oxidation Studies in a High-Pressure Loop ........... 263
Behavior of Beryllium Oxide Compacts Under Fast-
Neutron Irradiation .......................................... 264
Gross Damage Caused by Irradiation ........................ 266
Volume Increases of Irradiated BeO Compacts ............... 267
Microstructural Effects of Irradiation .................... 269
Effect of Irradiation on Single Crystals .................. 271
Damage Mechanisms ........................................ 272
9. DEVELOPMENT STUDIES FOR AVR - GERMAN PEBBLE-BED REACTOR ...... 276
Fuel Element Design Criteria ................................ 276
Fuel Composition and Fuel Management ......................... 279
Thermal Analysis of Core .................................... 284
Core Temperatures ......................................... 284
Thermal Radiation Within the Core ......................... 286
Thermal Stress in Graphite Spheres During Radiant
Cooling ......................... ........................ 289
Core Structural Investigations ............................... 291
Impact Studies of Graphite Spheres ....................... 291
Stress Analysis of Fueled Spheres ......................... 296
Fuel Element Development ..................................... 302
Evaluation of Graphite-Matrix Fuel Elements ............... 302
Nondestructive Inspection of Fueled-Graphite Spheres ...... 318
Assembly of Machined-Shell Elements ....................... 324
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Oak Ridge National Laboratory. Gas-Cooled Reactor Project Semiannual Progress Report: September 1963, report, January 29, 1964; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc100339/m1/9/: accessed April 19, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.