THROUGH-THICKNESS NOTCH DUCTILITY AND TENSION PROPERTIES AS A FUNCTION OF NEUTRON EXPOSURE TO A SIMULATED PRESSURE VESSEL WALL OF A302-B STEEL.
NAVAL RESEARCH LAB WASHINGTON D C
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Notch ductility and tension-property measurements have been made using specimens irradiated within a large steel test assembly simulating the pressure-vessel wall of a light-water-moderated power reactor. The A302-B steel specimens, spaced at intervals through the 6-in. thickness of the assembly, showed the greatest embrittlement and tensile property changes from irradiation locations nearest the fuel core, and correspondingly smaller changes farther from the core. Measured neutron fluxes of energies greater than 1 MeV, based upon an assumed fission spectrum, compared well with calculated spectrum neutron fluxes of energies greater than 1 MeV for all test assembly locations, thus providing the basis for future estimates of property changes through the thickness of heavy-walled reactor pressure vessels. Author
- Metallurgy and Metallography
- Radioactivity, Radioactive Wastes and Fission Products
- Fission Reactor Materials