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Publikováno v:
Journal of Materials Engineering and Performance. 4:25-31
Visioplastic analysis is used to compare strain fields produced in cylindrical aluminum billets extruded at elevated temperature through axially symmetric dies that have either a cosine or a conical profile. The visioplastic method consists of comput
Publikováno v:
Journal of Nuclear Materials. 210:216-225
The susceptibility of stainless steel 304 (SS304) to liquid metal embrittlement (LME) by cadmium (Cd) and cadmium-aluminum (Cd-Al) solutions was examined as part of a failure evaluation for SS304-clad cadmium reactor safety rods which had been expose
Autor:
John E. Marra, H.B. Peacock
Publikováno v:
Journal of the American Ceramic Society. 74:733-738
The cermet fuel (U{sub 3}O{sub 8} dispersed in Al) being considered thermodynamically unstable because of the potential for an exothermic metallothermic reduction reaction. This paper describes work performed to qualify the extent of reaction during
Autor:
T. M. Adams, Natraj Chandrasekar Iyer, R.L. Sindelar, H.B. Peacock, E. A. Howden, K. Marsden, B. R. Westphal, D. A. Sell, D. L. Fisher, K. J. Allen
Publikováno v:
12th International Conference on Nuclear Engineering, Volume 3.
United States Government funded national security nuclear non-proliferation projects have historically focused on power reactor spent fuel assemblies that contain weapons usable materials. More recently concern and emphasis have been focused on the s
Publikováno v:
Residual Stress, Fitness-For-Service, and Manufacturing Processes.
An expanding ring was developed that provided remote repair of the pour spout for a radioactive waste vitrification melter. This passive device used gas pressure to expand a metal ring against the irregularly shaped pour spout wall. Laboratory modeli
Autor:
H.B. Peacock
The core length in an extruded tube depends on the weight of powder in the billet core. In the past, the amount of aluminum powder needed to give a specified core length was determined empirically. This report gives a technique for calculating the we
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a03b828c8157203fb3f147c07ce2323a
https://doi.org/10.2172/782825
https://doi.org/10.2172/782825
Publikováno v:
MRS Proceedings. 556
The melt-dilute treatment technology program is focused on the development and implementation of a treatment technology for diluting highly enriched (>20% 235U) aluminum spent nuclear fuel to low enriched levels (235U and qualifying the LEU Al-SNF fo
Publikováno v:
MRS Proceedings. 608
The melt-dilute treatment technology is being developed to facilitate the ultimate disposition of highly enriched Al-Base DOE spent nuclear fuels in a geologic repository such as that proposed for Yucca Mountain. Currently, approximately 28 MTHM is e