摘要:
Zirconium-based corrosion resistant alloys for use primarily as a cladding material for fuel rods in a boiling water nuclear reactor which consist essentially of 0.5 to 2.5 weight percent bismuth, or alternatively, 0.5 to 2.5 weight percent of a mixture of tin and bismuth, 0.5-1.0 weight percent of a solute composed of a member selected from the group consisting of niobium, molybdenum, tellurium, and mixture thereof, alternatively, the solute will be composed of tellurium and will be in the range of 0.3-1.0 weight percent, and the balance being zirconium.
摘要:
This is a material for lining reactor fuel element cladding. Rather than using unalloyed zirconium, this invention utilized for a 0.1-4% tin alloy liner for the cladding. The very low metallic impurities to reduce solid solution strengthening and second phase formation and property variability from lot to lot, while using alloying to reduce the susceptibility to steam corrosion. Preferably, oxygen is controlled to a very low level as well, to provide a low, but fabricable, hardness in the alloyed liner material.
摘要:
A substance for reversibly sorbing and desorbing hydrogen is disclosed. The substance comprises a complex dispersing 0.8-20% by weight of one or more than two oxides selected from La, Ce, Nd, Pr, Sm and Eu into ZrV.sub.x (0.01.ltoreq.x.ltoreq.0.7).
摘要:
Superplastic metal alloys having a high defromation rate are disclosed. Their structure is characterized by the presence of at least two principal constituents, the major one of which is of a particulate globular or elongated shape while the minor one surrounds the first completely or partially in the form of a particle on the boundry surface of the major constituent which is less than 10 .mu.m thick. This invention can be applied to the shaping of alloys in the superplastic state at a high deformation rate above 100% min.sup.-1.
摘要:
This invention relates to a method for the production of non-evaporable ternary gettering alloys of the type Zr-M.sub.1 -M.sub.2 in which M.sub.1 is a metal chosen from the group comprising vanadium and niobium, and in which M.sub.2 is a metal chosen from the group comprising iron and nickel.
摘要:
Zirconium-titanium alloys containing at least one of the transition metal elements of iron, cobalt, nickel and copper are disclosed. The alloys consist essentially of about 1 to 64 atom percent titanium plus at least one element selected from the group consisting of about 15 to 27 atom percent iron, about 15 to 43 atom percent cobalt, about 15 to 42 atom percent nickel and about 35 to 68 atom percent copper, balance essentially zirconium plus incidental impurities, with the proviso that when iron is present, the maximum amount of titanium is about 25 atom percent, when cobalt is present, the maximum amount of titanium is about 54 atom percent and when nickel is present, the maximum amount of titanium is about 60 atom percent. The alloys in polycrystalline form are capable of being melted and rapidly quenched to the glassy state. Substantially totally glassy alloys of the invention evidence unusually high electrical resistivities of over 200 .mu..OMEGA.-cm.
摘要:
Continuous filaments of zirconium-copper glassy alloys containing at least one of the transition metal elements of iron, cobalt and nickel are disclosed. The filaments are substantially totally glassy and have a composition consisting essentially of about 1 to 68 atom percent copper plus at least one element selected from the group consisting of about 1 to 29 atom percent iron, about 1 to 43 atom percent cobalt and about 1 to 42 atom percent nickel, balance essentially zirconium plus incidental impurities. The glassy alloy filaments of the invention evidence unusually high electrical resistivities of over 200 .mu..OMEGA.-cm.
摘要:
Tubes for use in nuclear reactors fabricated from a quaternary alloy comprising 2.5-4.0 wt% Sn, 0.5-1.5 wt% Mo, 0.5-1.5 wt% Nb, balance essentially Zr. The tubes are fabricated by a process of hot extrusion, heat treatment, cold working to size and age hardening, so as to produce a microstructure comprising elongated .alpha. grains with an acicular transformed .beta. grain boundary phase.
摘要:
In a method of fabrication of nuclear reactor components such as fuel cans and pressure tubes, use is made of zirconium alloys such as Zircaloy 2 or Zircaloy 4 having an oxygen content of 0.14 to 0.25 % by weight. The components are subjected to an annealing operation at a temperature within the range of 400.degree. to 750.degree.C and especially 525.degree. to 750.degree.C over a period of approximately two hours, thus resulting in recrystallization.