Zobrazeno 1 - 10
of 13
pro vyhledávání: '"R.T. Purviance"'
Publikováno v:
Nuclear Engineering and Design. 146:195-206
Experiments were conducted in which molten aluminum alloys were injected into a 1.2 m deep pool of water. The parameters varied were (i) injectant material (8001 aluminum alloy and 12.3 wt% U-87.7 wt% Al), (ii) melt superheat (O to 50 K), (iii) water
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::07be9ce47dbd92aac4d64092ef9418ec
https://doi.org/10.1016/0029-5493(94)90329-8
https://doi.org/10.1016/0029-5493(94)90329-8
In May 1991, WSRC/SRL requested that ANL conduct five scoping tests in order to investigate the potential for self-triggered lithium/aluminum steam explosion in an SRS Septifoil. This work was to support the ongoing SAR Chapter 15 analysis for the K-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ff82248afcc2a863e668469e9feffd67
https://doi.org/10.2172/7231956
https://doi.org/10.2172/7231956
In May 1991, WSRC/SRL requested that ANL conduct five scoping tests in order to investigate the potential for self-triggered lithium/aluminum steam explosion in an SRS Septifoil. This work was to support the ongoing SAR Chapter 15 analysis for the K-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e81a84ba74941b2670e8af908692419b
https://doi.org/10.2172/10182194
https://doi.org/10.2172/10182194
Publikováno v:
Nuclear Engineering and Design. 7:442-454
The study of fast reactor safety is concerned with a number of areas, among which the possibility of core meltdown is of major interest. A number of factors might be involved in such an accident; this article deals with a study, experimentally and by
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f844c503d6b2bcb17e587c3160418521
https://doi.org/10.1016/0029-5493(68)90082-4
https://doi.org/10.1016/0029-5493(68)90082-4
Autor:
C.M. Walter, P.B. Henault, F.L. Willis, R.T. Purviance, A.B. Cohen, R.A. Noland, R.R. Smith, A. DeVolpi, C.E. Dickerman, J.F. Boland, J. Regis
Publikováno v:
Nuclear Engineering and Design. 12:381-390
Description of sodium loop experiments performed in the Transient Reactor Test (TREAT) Facility specifically to provide guidance for analyses on the behavior of an element which either has no sodium thermal bond between fuel and cladding or which, du
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d4d2c918b2772e1a2dfe3a41f97099a3
https://doi.org/10.1016/0029-5493(70)90052-x
https://doi.org/10.1016/0029-5493(70)90052-x
Publikováno v:
Nuclear Technology. 14:133-145
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::445f538905050ca5f3e8b450a0e80aac
https://doi.org/10.13182/nt72-a31128
https://doi.org/10.13182/nt72-a31128
Autor:
A.B. Cohen, L.E. Robinson, R.T. Purviance, C.E. Dickerman, A. De Volpi, J. Regis, F.L. Willis
Publikováno v:
Nuclear Engineering and Design. 12:391-406
Two experiments were performed on fuel failure and post-failure movements of fuel and coolant under power excursions. Test samples consisted of seven-pin clusters in instrumented integral sodium loops inserted into the TREAT reactor. One cluster was
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::23ffcb81324c5662f8f37bcf72facaa7
https://doi.org/10.1016/0029-5493(70)90053-1
https://doi.org/10.1016/0029-5493(70)90053-1