Zobrazeno 1 - 10
of 66
pro vyhledávání: '"H.E. McCoy"'
Autor:
H.E McCoy, J.R. DiStefano
Publikováno v:
International Journal of Refractory Metals and Hard Materials. 20:381-387
The overall objective of this study was to determine allowable design stresses for the solid-solution-strengthened alloy T-111 (Ta–8W–2Hf) to be used in a space power application at 300–650 °C. Tensile tests were conducted from 25 to 1100 °C
Autor:
P.L. Rittenhouse, H.E. McCoy
Publikováno v:
Journal of Nuclear Materials. 171:103-107
A testing program is in progress to define the tensile and creep properties of SA533 Grade B Class 1 steel at temperatures from 371 to 538 °C. The overall objective is to provide the data necessary to obtain ASME Code approval for use of this materi
Autor:
J.R. DiStefano, H.E. McCoy
In the design of the 60-W Isotopic Heat Source (IHS), a tantalum alloy (T-111) strength member serves as the primary containment shell for the IHS during operation (He-gas internal environment and inert gas or vacuum external environment). An outer H
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1f3b443357c7193ed9c5cadd853f5792
https://doi.org/10.2172/665943
https://doi.org/10.2172/665943
Autor:
H.E. McCoy
Publikováno v:
Nuclear and Chemical Waste Management. 3:51-57
The specific problem of developing a canister for the multibarrier waste isolation concept was considered. A conceptual design was developed for a canister that is relatively easy to fabricate, inspect, and handle. The design has the option of storin
Publikováno v:
Nuclear Technology. 66:161-174
Hastelloy-X is a potential structural material for use in gas-cooled reactor systems. In this application, data are necessary on the mechanical properties of base metal and weldments under realistic service conditions. The test environment studied wa
Autor:
H.E. McCoy
Publikováno v:
Journal of the Less Common Metals. 37:303-306
Autor:
H.E. McCoy
Publikováno v:
Journal of Nuclear Materials. 15:249-262
Because of the proposed use of beryllium as a fuelcladding material in a CO2-cooled reactor, the compatibility of beryllium and CO2 at elevated temperatures is of interest. The reported breakaway or nonprotective oxidation of beryllium in CO2 under c
Autor:
R.J. Kedl, D. Scott, P.R. Kasten, W. H. Cook, W. P. Eatherly, H.E. McCoy, C. R. Kennedy, E.S. Bettis, S.S. Kirslis, A.M. Perry, R.C. Robertson, D. K. Holmes, R.A. Strehlow
Publikováno v:
Nuclear Engineering and Design. 9:157-195
Graphite behavior under Molten-Salt Breeder Reactor (MSBR) conditions is reviewed and its influence on MSBR performance estimated. Based on the irradiation behavior of small-sized graphite specimens, a permissible reactor exposure for MSBR graphite i