Zobrazeno 1 - 5
of 5
pro vyhledávání: '"S. W. Heaberlin"'
Autor:
Kenneth L. Ferguson, R. C. Lloyd, S. W. Heaberlin, E. D. Clayton, R. D. Carter, J. Chao, B. B. Mikić, N. E. Todreas, D. H. Berwald, J. J. Duderstadt, S. L. Salem, J. S. Wu, G. Apostolakis, N. Ketzlach, E. K. Opperman, J. L. Straalsund, G. L. Wire, R. H. Howell, G. J. Zeman, D. L. Smith, Chia-Gee Wang, Anthony G. M. Davis, Edward J. Bouwer, John W. McKlveen, W. J. McDowell
Publikováno v:
Nuclear Technology. 42:1-4
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b95729f8079e95c92aeb7b76809401c
https://doi.org/10.13182/nt79-a32156
https://doi.org/10.13182/nt79-a32156
Publikováno v:
Nuclear Technology. 42:13-21
A study was made of 100 violations of criticality safety specifications reported over a 10-y period in the operations of fuel reprocessing plants. The seriousness of each rule violation was evaluated by assigning it a severity index value. The underl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::05148a31b496aca6263e54ae0b99ae03
https://doi.org/10.13182/nt79-a32158
https://doi.org/10.13182/nt79-a32158
The risk analysis model is applied to the assessment of the risk of Pu releases due to transportation accidents and package misclosure and degradation. The transport system and accident environment are described and release sequences postulated. Resu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2e74143bbfb55c3df512de17447ea6e1
https://doi.org/10.2172/7311606
https://doi.org/10.2172/7311606
Autor:
S. W. Heaberlin
In the fall of 1976, Battelle, Pacific Northwest Laboratories conducted a survey of eight facilities receiving plutonium shipments to determine the condition of plutonium shipping packages during shipment. This survey followed a similar survey conduc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4c9dcc16588f81a5169a1b39444b4bb7
https://doi.org/10.2172/1088039
https://doi.org/10.2172/1088039
Autor:
R. K. Marshall, W. N. Rausch, G. M. Hesson, G W McNair, W. D. Bennett, G W Neally, C. Nealley, R. L. Goodman, L L Kirg, L. J. Parchen, G. E. Russcher, S W Heaberlin, C. L. Wilson, J. P. Pilger, R E Schreiber, W D Meitzler, N. J. Wildung
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a series of experiments in the U-2 loop of the National Research Universal Reactor at Chalk River, Ontario, Canada. The first of these experiments includes u
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1145bfe86e4b23a2ac9b51a8e6a527c7
https://doi.org/10.2172/1072978
https://doi.org/10.2172/1072978