Materials Science and Technology: A Comprehensive TreatmentRobert W. Cahn, Brian R. T. Frost, Peter Haasen, Edward J. Kramer Corrosion and corrosion protection is one of most important topics in applied materials science. Corrosion science is not only important from an economic point of view, but, due to its interdisciplinary nature combining metallurgy, materials physics and electrochemistry, it is also of high scientific interest. Nowadays corrosion science even gets new impetus from surface science and polymer chemistry. This two-volume reference work belonging to the well renown series Materials Science and Tehcnology provides the reader with a sound and broad survey on the whole subject - from the fundamentals to the latest research results. Written by a team of international top-experts it will become an indispensable reference for any materials scientist, physicist or chemist involved in corrosion science. |
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Results 1-3 of 60
Page 224
... annealing curves for pure Cu after irradiation at 4.2 K with fast neutrons ( nf ) and MeV electrons ( e ̄ ) to typical doses of 10-5 dpa . The annealing temperature T is normalized to the melting temperature of Cu . The dashed curve la ...
... annealing curves for pure Cu after irradiation at 4.2 K with fast neutrons ( nf ) and MeV electrons ( e ̄ ) to typical doses of 10-5 dpa . The annealing temperature T is normalized to the melting temperature of Cu . The dashed curve la ...
Page 398
... annealing for several hours at fixed temperatures . Loss of fission products from the fuel to the atmosphere of the annealing crucible as a function of temperature was initially as- sumed to be by volume diffusion only and the data were ...
... annealing for several hours at fixed temperatures . Loss of fission products from the fuel to the atmosphere of the annealing crucible as a function of temperature was initially as- sumed to be by volume diffusion only and the data were ...
Page 443
... annealing curves , copper 224 annealing experiments - beryllium , post - irradiation 320 - interstitials 198 annealing treatments , zirconium alloys 17 argon , fuel pin fill gas 401 armor materials , fusion reactors 279 ASME code ...
... annealing curves , copper 224 annealing experiments - beryllium , post - irradiation 320 - interstitials 198 annealing treatments , zirconium alloys 17 argon , fuel pin fill gas 401 armor materials , fusion reactors 279 ASME code ...
Contents
Zirconium Alloys in Nuclear Applications | 2 |
Structural Materials | 8 |
Nuclear Waste Materials | 12 |
Copyright | |
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Materials Science and Technology: A Comprehensive Treatment Robert Wolfgang Cahn,Peter Haasen,Edward J. Kramer No preview available - 1994 |
Common terms and phrases
alloys amorphous annealing ASME ASTM ASTM-STP atoms austenitic austenitic steels behavior breeder burnup Candu carbon chemical cladding components Conf coolant core corrosion resistance Cr 1 Mo crack growth creep damage defects density diffusion displacement ductility effects embrittlement energy fabrication fatigue ferritic ferritic steels Figure fluence flux fracture mechanics fracture toughness fuel pins grain boundaries graphite heat helium high temperature HTGR hydrogen impurities increase interstitials irradiation layer loops ments microstructure mixed oxide fuel n/cm² neutron irradiation niobium NPPs nuclear observed operation oxide oxygen parameters perature phase precipitates pressure tubes pressure vessel primary Proc radiation reduced requirements sodium spike stainless steel steam stress corrosion cracking structural materials surface swelling Table tensile tests thermal tion tritium ture vacancies water chemistry water reactor yield strength Zircaloy Zr alloys Zr Nucl