Zobrazeno 1 - 9
of 9
pro vyhledávání: '"R. R. Hobbins"'
Publikováno v:
Nuclear Technology. 184:181-197
Modular high-temperature gas-cooled reactors (MHTGRs) offer a high degree of passive safety. The low power density of the reactor and the high heat capacity of the graphite core result in slow transients that do not challenge the integrity of the rob
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bc01c2bc6459def4c4752ce4747074d5
https://doi.org/10.13182/nt184-181
https://doi.org/10.13182/nt184-181
Autor:
L. B. Lundberg, R. R. Hobbins
Publikováno v:
SAE Technical Paper Series.
The success of the development of nuclear thermal propulsion devices and thermionic space nuclear power generation systems depends on the successful utilization of nuclear fuel materials at temperatures in the range 2000 to 3500 K. Problems associate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::11f1a80b806eff94ddadafb0fb1e3074
https://doi.org/10.4271/929077
https://doi.org/10.4271/929077
Publikováno v:
Oxidation of Metals. 8:409-455
By use of radiotracer techniques, the iron self-diffusion coefficient in ferrous sulfide single crystals above 620 K was found to be D = D0δ exp {−[(81±4) + (84±20)δ]/RT}where the exponential units are kJ/mole, D0 is 1.7± 0.1×10−2 and 3.0±
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::701e0c10bfb14130b39d79774a8a09a5
https://doi.org/10.1007/bf00603390
https://doi.org/10.1007/bf00603390
Autor:
G. L. Cano, R. W. Ostensen, M. F. Young, A. M. Sokolovsky, M. Livolant, J. Gauvain, A. Hoffmann, M. Baines, S. J. Board, N. E. Buttery, R. W. Hall, S. R. Bierman, B. M. Durst, E. D. Clayton, B. W. Howes, Marilyn M. Osterhout, R. T. Lahey, P. S. Kamat, S. R. Speidel, W. H. Plettenberg, H. J. Sutherland, J. E. Smaardyk, L. A. Kent, Dong H. Nguyen, G. W. Hollenberg, J. L. Jackson, J. A. Basmajian, David W. Varela, William E. Kastenberg, Vijay K. Dhir, P. Wydler, W. Heer, P. Stiller, H. U. Wenger, M. V. Ramaniah, H. C. Jain, S. K. Aggarwal, S. A. Chitambar, V. D. Kavimandan, A. I. Almaula, P. M. Shah, A. R. Parab, V. L. Sant, A. Delbrassine, L. Smith, J. M. Beeston, R. R. Hobbins, G. W. Gibson, W. C. Francis, H. C. Burkholder, E. L. J. Rosinger, T. V. Krishan, R. J. Gehrke, J. I. Anderson, D. H. Meikrantz
Publikováno v:
Nuclear Technology. 49:1-8
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4397c4a9e7a493b9c349f2901f35c34e
https://doi.org/10.13182/nt80-a32500
https://doi.org/10.13182/nt80-a32500
Publikováno v:
Nuclear Technology. 49:136-149
Uranium aluminide powder production, fuel plate fabrication development, and irradiaton performance of more than 1700 fuel elements during 10 yr of operational service at Idaho National Engineering Laboratory are discussed. The purpose of this paper
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bada3b9fa12f518e063cb9734e0b3234
https://doi.org/10.13182/nt80-a32515
https://doi.org/10.13182/nt80-a32515
Autor:
W. E. Roake, T. T. Claudson, R. L. Simons, W. N. McElroy, L. D. Blackburn, S. D. Harkness, R. Grappel, S. G. McDonald, J. L. Straalsund, G. L. Guthrie, E. E. Bloom, J. R. Weir, W. G. Wolfer, J. P. Foster, F. A. Garner, P. J. Ring, K. D. Challenger, H. J. Busboom, L. A. Neimark, J. D. B. Lambert, W. F. Murphy, C. W. Renfro, B. F. Rubin, T. J. Black, W. K. Appleby, J. D. Stephen, R. F. Hilbert, T. D. Gulden, C. L. Smith, D. P. Harmon, W. W. Hudritsch, M. Coquerelle, J. Gabolde, R. Lesser, P. Werner, W. J. Lackey, F. J. Homan, A. R. Olsen, M. Conte, M. Mouchnino, F. K. Schmitz, B. L. Harbourn, M. S. Beck, A. Biancheria, W. H. McCarthy, K. J. Perry, G. R. Hull, J. W. Bennett, R. J. Beaver, A. E. Richt, O. M. Stansfield, G. E. Russcher, A. L. Pitner, G. L. Copeland, R. G. Donnelly, W. R. Martin, J. A. Basmajian, D. E. Mahagin, H. C. F. Ripfel, D. E. Baker, W. E. Ray, R. L. Miller, S. L. Schrock, G. A. Whitlow, E. Berkey, G. G. Sweeney, W. M. Hickam, J. C. Tobin, R. A. Moen, D. J. Ayres, T. M. Cullen, C. R. Brinkman, G. E. Korth, R. R. Hobbins, J. M. Steichen, Lee A. James, A. J. Lovell, W. E. Pennell
Publikováno v:
Nuclear Technology. 16:3-11
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dba27d2fcb02692f3d90c855cc735ae3
https://doi.org/10.13182/nt72-a31169
https://doi.org/10.13182/nt72-a31169
Publikováno v:
Nuclear Technology. 16:297-307
Comparing data obtained from tests conducted on unirradiated Type 316 stainless steel in either the solution annealed or solution annealed and aged condition showed that aging was beneficial in imp...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b195e8a12f7f6b63bf061e7604860cd8
https://doi.org/10.13182/nt72-a31195
https://doi.org/10.13182/nt72-a31195