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 352
... pellet o Limited restructuring O + Powder 20 A A 10 0 Large diameter vibrocompacted 2 5 6 Annular pellet Vibrocompacted 9 10 11 12 Figure 11-8 . Mixed oxide fuel fission gas release as a function of burnup and power ( after Lambert et ...
... pellet o Limited restructuring O + Powder 20 A A 10 0 Large diameter vibrocompacted 2 5 6 Annular pellet Vibrocompacted 9 10 11 12 Figure 11-8 . Mixed oxide fuel fission gas release as a function of burnup and power ( after Lambert et ...
Page 399
... pellet ) to 0.6 , resulting in barium defi- -- ciency at the pellet center and a slight ex- cess at the region near 0.6 relative radius . No separated barium phases were ob- served and there was no evidence for axial migration of barium ...
... pellet ) to 0.6 , resulting in barium defi- -- ciency at the pellet center and a slight ex- cess at the region near 0.6 relative radius . No separated barium phases were ob- served and there was no evidence for axial migration of barium ...
Page 400
... pellet gaps and spacer grids and no evidence for ce- sium migration . Ceramography showed a pellet - cladding gap of 50 to 100 μm ; how- ever , extensive bonding of the fuel to the clad was also seen and postulated to con- tain a cesium ...
... pellet gaps and spacer grids and no evidence for ce- sium migration . Ceramography showed a pellet - cladding gap of 50 to 100 μm ; how- ever , extensive bonding of the fuel to the clad was also seen and postulated to con- tain a cesium ...
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