Zobrazeno 1 - 10
of 15
pro vyhledávání: '"C.F. Leitten"'
Publikováno v:
Journal of Nuclear Materials. 1:136-144
The Army Package Power Reactor (APPR-1) at Fort Belvoir, Virginia, is currently operating with a control rod which contains a boron-bearing neutron absorber section. This component is a welded rectangular parallelepiped, in which the sides consist of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::97bba3b31afb1b5da22050b29729df67
https://doi.org/10.1016/0022-3115(59)90047-9
https://doi.org/10.1016/0022-3115(59)90047-9
Autor:
W.J. Kucera, C.F. Leitten
The integrity and suitability of 35 vol.% U/sub 3/ O/sub 8/ dispersion in Al as a fuel for foreign reactors were determined. The fuel was exposed in the beryllium reflector of the MTR. Sample fabrication and conditions of exposurne are described, and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fbaa8763f3b7c4aac90f580e47a3ca64
https://doi.org/10.2172/4297618
https://doi.org/10.2172/4297618
Autor:
C.F. Leitten, W.C. Thurber
A series of im-pile fuel sample irradiation experiments was initiated to obtaim radiation damage information on fuel material combinations applicable to Foreign Reactor Program Fuel Elements where U/sup 235/ enrichment is limited to 20%. The series o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0858a66fa2965546ce86096d8beda44e
https://doi.org/10.2172/4308397
https://doi.org/10.2172/4308397
Autor:
C.F. Leitten, W.C. Thurber
>lium reflector of the MTR to burn-up values of 20, 40, 60, and 80% of the U/sup 235/ atoms is described. The fuel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::edebc16c355f603d7a2a1c66a1f5612f
https://doi.org/10.2172/4289861
https://doi.org/10.2172/4289861
Autor:
R.J. Beaver, C.F. Leitten
>The corrosion resistance of mantensitic and ferritic austenitic stainless steels and carbon steels in pressurized water at 500 to 600 deg F is compared. Included are specific out-of-pile data for austenitic stainless steels, AISI types types 410, 42
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::737e79afb40b4d9f63f97ac31c760266
https://doi.org/10.2172/4702067
https://doi.org/10.2172/4702067
Autor:
C.F. Leitten, W.C. Thurber
The following data summarize the results of calculations presented in this report to determine the irradiation testing for Phase I of Irradiation Request ORNLMTR-35. This phase of the program entails exposure of a 48 wt.% U-3 wt.% Si-49 wt.% Al alloy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2486a93882056e2cc7f0e31f53a46b4e
https://doi.org/10.2172/4282923
https://doi.org/10.2172/4282923
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