Materials Science and Technology: A Comprehensive Treatment, Volume 1; Volume 2, Part 1; Volume 10, Part 1Robert W. Cahn, Peter Haasen, Edward J. Kramer The first of two volumes in this series to deal with the information required for the use of materials in the nuclear power industry. The two volumes together contain the most comprehensive collection of information ever published in nuclear materials. Contents: Walters/Hofman: Metallic Fast Reactor Fuels. Snelgrove/Hofman: Dispersion Fuels. Strain/Lambert: Oxide Fuels. Blank: Non-Oxide Ceramic Nuclear Fuels. Kelly: Nuclear Reactor Moderator Materials. Garner: Cladding. |
From inside the book
Results 1-3 of 90
Page 243
... porosity intended for later ac- commodation of fission gas swelling . To produce thermally stable fuel Blank found attention must be given not only to the porosity size distribution but also to the shape of the pores . P - type pellets ...
... porosity intended for later ac- commodation of fission gas swelling . To produce thermally stable fuel Blank found attention must be given not only to the porosity size distribution but also to the shape of the pores . P - type pellets ...
Page 287
... Porosity on Thermal Conductivity From the role porosity plays in the sin- ter kinetics , see Sec . 4.3.3 , and the roles of closed and open porosity under irradia- tion , see Secs . 4.5.3.1 and 4.5.3.2 , one may expect that open and ...
... Porosity on Thermal Conductivity From the role porosity plays in the sin- ter kinetics , see Sec . 4.3.3 , and the roles of closed and open porosity under irradia- tion , see Secs . 4.5.3.1 and 4.5.3.2 , one may expect that open and ...
Page 339
... porosity . However , to quantify the role of the sta- ble porosity during irradiation period C , especially in structural zone IV , a quantita- tive model of the fuel structure and its changes with burnup is necessary in rela- tion to ...
... porosity . However , to quantify the role of the sta- ble porosity during irradiation period C , especially in structural zone IV , a quantita- tive model of the fuel structure and its changes with burnup is necessary in rela- tion to ...
Contents
Dr Hubert Blank Dr John D B Lambert | 2 |
Nuclear Reactor Moderator Materials | 5 |
Irradiation Performance of Cladding and Structural Steels | 6 |
Copyright | |
14 other sections not shown
Other editions - View all
Materials Science and Technology: A Comprehensive Treatment Robert Wolfgang Cahn,Peter Haasen,Edward J. Kramer No preview available - 1994 |
Common terms and phrases
Al-U alloy alloy aluminum atoms behavior burnup carbide carbide and nitride carbide fuel carbon ceramic changes cladding coefficient Conf coolant creep curve decrease diffusion dispersion fuel EBR-II effect energy fabrication Fast Breeder Reactor fast reactor FCCI Figure fission density fission products fission rate fraction fuel elements fuel meat fuel particles fuel plates fuel rod fuel-cladding gas release grain boundary graphite He-bonded high burnup IAEA in-pile increase irradiation kW/m La Grange Park material matrix Matzke mechanism metallic fuel MX-type fuels neutron nitride nitride fuels Nucl operation oxide oxygen P₂ pellet perature phase plutonium pore porosity Proc properties radial ratio reac reaction Reactor Fuel shown in Fig sintering solid stoichiometric stress structure surface Table temperature thermal conductivity thermal expansion tion ture U3Og U3Si UO₂ uranium volume Zircaloy zirconium zone