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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Page 169
... graphite have been licensed ( Wieser et al . , 1985 ) . The idea of transporting and storing radioac- tive material in the same metal casks was envisaged for the " Castor " and " Pollux " casks in about 1976 by GNB in Germany . The main ...
... graphite have been licensed ( Wieser et al . , 1985 ) . The idea of transporting and storing radioac- tive material in the same metal casks was envisaged for the " Castor " and " Pollux " casks in about 1976 by GNB in Germany . The main ...
Page 283
... Graphite is unique among materials in that the sputtering rate can vary with tem- perature due to chemically enhanced and sublimation enhanced sputtering . As shown in Fig . 10-41 for H and D on C , enhanced chemical erosion occurs in ...
... Graphite is unique among materials in that the sputtering rate can vary with tem- perature due to chemically enhanced and sublimation enhanced sputtering . As shown in Fig . 10-41 for H and D on C , enhanced chemical erosion occurs in ...
Page 287
... graphite . Earlier studies ( Wilson , 1984 ) with metals have shown the trap density due to radiation damage to be as high as 1 at . % . At this level of trapping , saturation with tritium in the large amount of graphite to be used in a ...
... graphite . Earlier studies ( Wilson , 1984 ) with metals have shown the trap density due to radiation damage to be as high as 1 at . % . At this level of trapping , saturation with tritium in the large amount of graphite to be used in a ...
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