MECHANICAL PROPERTIES OF ALLOYS OF MAGNESIUM AND OF ZIRCONIUM

Technical Report · Fri Oct 30 23:00:00 EST 1959

OSTI ID:4266590

Olds, G C.E.; Harris, J E; Roberts, R R; Smith, T B; Draper, J H.M.; Raine, T; Geach, G A; Hartree, O P

Important factors limiting design in the carbon dioxide cooled, graphite moderated, natural uranium reactor are the properties of structural support and canning materials for the fuel element. In the case of structural support materials, corrosion resistance and creep resistance at high temperatures are of major importance. New alloys of magnesium and zirconium have heen studied and assessed with the aim of obtaining alloys of high creep strength at 400 to 45O deg C, acceptable for application in the reactor. Magnesium alloys with low neutron absorption cross section, for application as canning materials, have also been studied in order to develop a suitable material of high ductility and adequate strength over a wide temperature range. Properties of magnesium canaing materials which were considered are high temperature ductility at low rates of strain, grain size stabtlity and the effect of prestrain on grain growth, creep strength at very low stresses at 450 to 500 deg C, intercrystalline cavitation during deformation, and weldability and weld properties. (auth)

• Research Organization: British Thomson-Houston Co., Ltd., Rugby, Eng.; Metropolitan- Vickers Electrical Co., Ltd., Manchester, Eng.; Associated Electrical Industries, Ltd., Aldermaston, Berks, Eng.
• NSA Number: NSA-13-006811
• OSTI ID: 4266590
• Report Number(s): A/CONF.15/P/1455
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ABSORPTION
CANNING
CARBON DIOXIDE
CAVITATION
CORROSION
CREEP
CROSS SECTIONS
DEFORMATION
DUCTILITY
EXPANSION
FUEL ELEMENTS
GAS COOLANT
GRAIN SIZE
GRAPHITE MODERATOR
LIQUID FLOW
MAGNESIUM ALLOYS
MECHANICAL PROPERTIES
METALLURGY AND CERAMICS
NEUTRON BEAMS
REACTORS
STABILITY
STRESSES
TEMPERATURE
URANIUM
WELDING
WELDS
ZIRCONIUM ALLOYS