Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Donald D. Lanning"'
Publikováno v:
Nuclear Technology. 102:210-231
Research to define the behavior of Zircaloy-clad light water reactor (LWR) UO[sub 2] fuel irradiated to high burnup levels was conducted as part of the High Burnup Effects Program (HBEP). The HBEP was a 12-yr program that ultimately acquired, charact
Autor:
Mark W. Shaver, Donald D. Lanning
The hypothesis of this paper is that the Zircaloy clad fuel source is minimal and that secondary startup neutron sources are the significant contributors of the tritium in the RCS that was previously assigned to release from fuel. Currently there are
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f6c9a3e568d2ac6b9dd366de8e647080
https://doi.org/10.2172/991094
https://doi.org/10.2172/991094
Autor:
Mitchel E. Cunningham, Kenneth J. Geelhood, Walter G. Luscher, Donald D. Lanning, Harold E. Adkins, David J. Senor
The latest versions of the fuel performance codes, FRAPCON-3 and FRAPTRAN were examined to determine if the codes are intrinsically conservative. Each individual model and type of code prediction was examined and compared to the data that was used to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::151adb80041901853496bc6b74aa85f8
https://doi.org/10.2172/969175
https://doi.org/10.2172/969175
Autor:
Kenneth C. Radford, Bruce M. Argall, Herbert W. Keller, Richard C. Goodspeed, Lester Goldstein, Alfred A. Strasser, Norbert Eickelpasch, Reinhard W. Seepolt, Johann Müllauer, Werner Spalthoff, Hiromi Kanbe, Tadashi Inoue, Toshi Tomizawa, Hiroaki Kōyama, Hiroharu Itami, Gary A. Hughes, Sudarshan K. Loyalka, Gerald A. Schlapper, O. K. Tallent, James C. Mailen, David O. Campbell, S. R. Buxton, K. Lassmann, Timm Preusser, Mitchel E. Cunningham, Donald D. Lanning, Norman P. Goldstein, William H. Todt, Alex D. Service
Publikováno v:
Nuclear Technology. 60:337-341
Publikováno v:
Nuclear Technology. 50:95-107
Various interacting mechanical and thermal processes operate in a fuel rod during irradiation. Fuel rod modeling codes are written to predict the outcome of these interactions. These two questions concern the statistical confidence limits on thermoco
Autor:
Donald D. Lanning
Publikováno v:
Nuclear Technology. 56:565-574
Thermally induced cracking of the UO2 fuel pellets undoubtedly results in some reduction of the effective fuel thermal conductivity, relative to that for solid UO2. This effect may be approximated ...
Autor:
G. Apostolakis, T. L. Chu, J. A. Figg, N. J. McCormick, R. E. Schenter, F. Schmittroth, Robert E. Einziger, Bobby R. Seidel, Chong Chiu, Neil E. Todreas, Warren M. Rohsenow, Vladimír Balek, Miroslav Vobořil, Václav Baran, Jungchung Jung, J. Gilbert, R. Marfaing, H. Vidal, Sümer Şahin, Jacques Ligou, Donald D. Lanning, Bruce O. Barnes, W. A. Scheffler
Publikováno v:
Nuclear Technology. 50:1-4
Publikováno v:
Nuclear Technology. 56:340-350
An alternate thermal-mechanical behavior model for cracked UO/sub 2/ pelletized fuel is presented. It is recognized that fuel cracking and relocation cause some of the initial pellet-cladding gap (the ''free area'') to be moved into the fuel in the f
Publikováno v:
Nuclear Technology. 60:420-429
Irradiation data collected from test fuel rods that were identically built and operated may be used to define a range of normal performance for a specific fuel rod design. By comparing the data to computer code calculations, it is possible to define
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