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 400
... fission gas release ( < 0.2 % to 1.1 % ) show sharp in- terpellet gaps and spacer grids clearly de- fined . For high fission gas release ( 11.2 % ) , cesium redistribution is clearly evident in gamma scans , and pellet boundaries are ...
... fission gas release ( < 0.2 % to 1.1 % ) show sharp in- terpellet gaps and spacer grids clearly de- fined . For high fission gas release ( 11.2 % ) , cesium redistribution is clearly evident in gamma scans , and pellet boundaries are ...
Page 405
... fission yield of 137Cs is about 10 times that of 1291. Cesium car- rier was found to have no effect on Cs release . It is possible that the I and Cs are present as Cs2ZrI6 , which is ... fission gas . Fuels run at 12.2 Spent Fuel 405.
... fission yield of 137Cs is about 10 times that of 1291. Cesium car- rier was found to have no effect on Cs release . It is possible that the I and Cs are present as Cs2ZrI6 , which is ... fission gas . Fuels run at 12.2 Spent Fuel 405.
Page 447
... fission gas pressure , end - of - life , fuel pins 346 fission gas release - CANDU fuel 405 - LWR fuel 397 - mixed oxide fuel pins 350 prototype mixed oxide fuel pins 363 fission products mass distribution 343 - waste materials 393 ...
... fission gas pressure , end - of - life , fuel pins 346 fission gas release - CANDU fuel 405 - LWR fuel 397 - mixed oxide fuel pins 350 prototype mixed oxide fuel pins 363 fission products mass distribution 343 - waste materials 393 ...
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