Zobrazeno 1 - 10
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pro vyhledávání: '"August W. Cronenberg"'
Autor:
August W. Cronenberg
Publikováno v:
Nuclear Technology. 97:97-112
In this paper Zircaloy oxidation and hydrogen generation data for the loss-of-fluid test (LOFT) FP-2 test are presented and compared with findings from other severe fuel damage experiments. In the LOFT FP-2 test, the majority of hydrogen generation o
Autor:
August W. Cronenberg
Publikováno v:
Nuclear Technology. 93:221-239
Zircaloy oxidation and hydrogen generation data from several in-pile severe fuel damage experiments are presented and compared. Common findings indicate that the extent of bundle oxidation is large...
Autor:
F. S. Gunnerson, August W. Cronenberg
Publikováno v:
Nuclear Technology. 49:380-391
An initial period of film boiling has been identified as a key element in the chain of events leading to a large-scale vapor explosion. From theoretical considerations, the conditions requi...
Autor:
Akio Gofuku, Hidekazu Yoshikawa, Shunsuke Hayashi, Kenji Shimizu, Jiro Wakabayashi, Chun-Der Wu, Joel Weisman, August W. Cronenberg, Daniel J. Osetek, Chang K. Park, Robert A. Bari, William Kerr, Bernard R. Bandini, Anthony J. Baratta, Victor R. Fricke, Kenneth C. Okafor, Tunc Aldemir, Paul A. Haas, Norikatsu Yokota, Shigehiro Shimoyashiki, G. Pierini, B. Spelta, S. Maffi, G. Modica, G. Perez, E. Possagno, Kunihiko Takeda, Hatsuki Onitsuka, Heiichiro Obanawi, Shin Saito, Archie A. Harms, Greg Cripps, John M. Cimbala, Daniel E. Hughes, Samuel H. Levine, Dhushy Sathianathan, Yassin A. Hassan
Publikováno v:
Nuclear Technology. 81:307-311
Publikováno v:
Journal of Nuclear Materials. 67:67-76
An important aspect of Liquid-Metal Fast Breeder Reactor (LMFBR) safety analysis is an accurate description of the transport phenomena of the various reactor materials during a hypothetical core-disruptive accident. For the case of an accident sequen
Autor:
August W. Cronenberg, Richard Coats
Publikováno v:
Nuclear Engineering and Design. 36:261-272
Analysis of crystallization kinetics for UO 2 in sodium [1] has been extended to UC and UN. Calculated results for all three fuels indicate that the fuel-sodium contact temperature is well below the homogeneous crystallization temperature, and that t
Publikováno v:
Nuclear Engineering and Design. 47:195-225
An important problem related to the assessment of the recriticality potential for an LMFBR following a core disruptive accident is an understanding of the freezing phenomena of molten fuel on a cold structure which may prevent fuel dispersal and subs
Autor:
August W. Cronenberg, Daniel J. Osetek
Publikováno v:
Nuclear Technology. 81:347-359
The chemical reaction kinetics of fission product iodine and cesium released from fuel to a steam/hydrogen atmosphere are investigated at conditions associated with severe core damage accidents. Th...
Publikováno v:
Journal of Nuclear Materials. 78:390-407
During high-temperature transients on zircaloy clad nuclear fuel rods, both external and internal cladding oxidation have been observed. The result of these oxidation processes is to embrittle the cladding, making it susceptible to brittle fracture.
Publikováno v:
Nuclear Technology. 67:312-325
Fuel melting in severe core damage accidents will lead to the rapid release of fission gas from the fuel matrix and the volatilization of low boiling point metallic inclusions, which can be expecte...