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 134
... cycle fatigue " ( LCF ) endurance is controlled mainly by crack growth of small cracks ( about 0.01-0.1 mm ) generated early during cycling . In the high - cycle fa- tigue ( HCF ) range ( > 106 cycles ) the fa- tigue endurance is ...
... cycle fatigue " ( LCF ) endurance is controlled mainly by crack growth of small cracks ( about 0.01-0.1 mm ) generated early during cycling . In the high - cycle fa- tigue ( HCF ) range ( > 106 cycles ) the fa- tigue endurance is ...
Page 411
... cycle 2 and 3 rinse solutions represents dissolu- tion of fuel fines , and that the remainder is dissolution of secondary phases . Since the total amount of material is less than 1 mg , it would be very hard to locate on the fuel test ...
... cycle 2 and 3 rinse solutions represents dissolu- tion of fuel fines , and that the remainder is dissolution of secondary phases . Since the total amount of material is less than 1 mg , it would be very hard to locate on the fuel test ...
Page 412
... cycle 1 , but slightly less for cycle 2. These data are very suggestive of preferential release of nuclides from the outer rim of the fuel pellet , which contains a large proportion of the higher actinides . Interpretation of the Pu ...
... cycle 1 , but slightly less for cycle 2. These data are very suggestive of preferential release of nuclides from the outer rim of the fuel pellet , which contains a large proportion of the higher actinides . Interpretation of the Pu ...
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