Zobrazeno 1 - 10
of 230
pro vyhledávání: '"E. E. Morris"'
Publikováno v:
Nuclear Technology. 154:95-106
This paper describes the results of a study that uses the thermal performance of the repository to establish chemical separations and transmutation criteria for commercial spent nuclear fuel of ben...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::859e06746256a61479153f0042cc56fc
https://doi.org/10.13182/nt06-3
https://doi.org/10.13182/nt06-3
The GNEP program envisions continuing the use of light-water reactors (LWRs), with the addition of processing the discharged, or spent, LWR fuel to recover actinide and fission product elements, and then recycling the actinide elements in sodium-cool
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f2d1d2c42579c6c6be6323df2500d886
https://doi.org/10.2172/924690
https://doi.org/10.2172/924690
Autor:
E. E. Morris
The sensitivities of various output parameters to selected input parameters in unprotected combined loss of heat-sink and loss-of-flow (ULOHS), loss-of-flow (ULOF), and transient-overpower (UTOP) accidents are explored in this report. This line of in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ac2d748a5a0558b1a1de8c62cedb59e5
https://doi.org/10.2172/948804
https://doi.org/10.2172/948804
Autor:
E. E. Morris, T.H. Bauer
This report satisfies Milestone 4295 for Work Package A0403K11. The long-term behavior of TRISO nuclear reactor fuel in a geologic repository is examined in terms of its durability and thermal impact. The TRISO fuel concept, under development at Gene
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::73fea0e28131cb2f006204badad84087
https://doi.org/10.2172/885503
https://doi.org/10.2172/885503
Autor:
S. M. Frank, T. H. Fanning, Roald Wigeland, W. L. Ebert, L. R. Morss, M. C. Hash, E. E. Morris, T. P. O'Holleran
As part of the spent fuel treatment program at Argonne National Laboratory (ANL), a ceramic waste form is being developed for disposition of the salt waste stream generated during the treatment process. Ceramic waste form (CWF) degradation and radion
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a35a61ce1bb2b32119ea4ff16647cf5d
https://doi.org/10.2172/809171
https://doi.org/10.2172/809171
Autor:
E. E. Morris
Publikováno v:
Refugee Survey Quarterly. 15:1-1
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::76cbadd186e20a00da10b56b93cef9cb
https://doi.org/10.1093/rsq/15.2.1-a
https://doi.org/10.1093/rsq/15.2.1-a