Zobrazeno 1 - 10
of 17
pro vyhledávání: '"D. K. Morton"'
Autor:
D. K. Morton, Spencer D. Snow
The objective of the work reported herein was to determine the ability of the Multi- Canister Overpack (MCO) canister design to maintain its containment boundary after an accidental drop event. Two test MCO canisters were assembled at Hanford, prepar
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8d2008212c9ae6c24975e5f220538d76
https://doi.org/10.2172/1194007
https://doi.org/10.2172/1194007
Publikováno v:
Practical Failure Analysis. 3:43-49
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b09fa6b089964a0c6406b5c77171745f
https://doi.org/10.1007/bf02715932
https://doi.org/10.1007/bf02715932
Autor:
D. K. Morton
Following the defunding of the Yucca Mountain Project, it is reasonable to assume that commercial used fuel will remain in storage for a longer time period than initially assumed. Previous transportation task work in FY 2011, under the Department of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::75454e932a656b8baddf925119cd5650
https://doi.org/10.2172/1055991
https://doi.org/10.2172/1055991
Publikováno v:
Volume 7: Operations, Applications and Components.
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code is primarily a stress-based acceptance criteria code. These criteria are applicable to force, displacement, and energy-controlled loadings and ensure a factor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::86bdae75274a739bfa5e3a3528e45a60
https://doi.org/10.1115/pvp2009-77122
https://doi.org/10.1115/pvp2009-77122
Autor:
D. K. Morton
Stainless steels are used for the construction of numerous spent nuclear fuel or radioactive material containers that may be subjected to high strains and moderate strain rates during accidental drop events. Mechanical characteristics of these base m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::870de20519110a358b9f7cd6393d843b
https://doi.org/10.2172/933178
https://doi.org/10.2172/933178
Publikováno v:
Volume 7: Operations, Applications and Components.
Stainless steels are used for the construction of numerous spent nuclear fuel or radioactive material containers that may be subjected to high strains and moderate strain rates during accidental drop events. Mechanical characteristics of these base m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::12fd09b5cde09e5738ef4a3769a7f79b
https://doi.org/10.1115/pvp2008-61215
https://doi.org/10.1115/pvp2008-61215
Publikováno v:
Volume 6: Materials and Fabrication.
The Idaho National Laboratory (INL) is conducting moderate strain rate (10 to 200 per second) research on stainless steel materials in support of the Department of Energy’s (DOE) National Spent Nuclear Fuel Program (NSNFP). For this research, strai
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ef9bd8108f3582fac3149e523bcc2f5d
https://doi.org/10.1115/pvp2007-26096
https://doi.org/10.1115/pvp2007-26096
Publikováno v:
Volume 7: Operations, Applications and Components.
Stainless steels are used for the construction of numerous spent nuclear fuel or radioactive material containers that may be subjected to high strains and moderate strain rates during accidental drop events. Mechanical characteristics of these base m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4c9c8f0781dc3bd6ab5b2624882d858e
https://doi.org/10.1115/pvp2007-26182
https://doi.org/10.1115/pvp2007-26182
Publikováno v:
Volume 7: Operations, Applications, and Components.
Stainless steels are used for the construction of numerous spent nuclear fuel or radioactive material containers that may be subjected to high strains and moderate strain rates (10 to 200 per second) during accidental drop events. Mechanical characte
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f24f9dea6c6a9faa613e0c558f6034b5
https://doi.org/10.1115/pvp2005-71133
https://doi.org/10.1115/pvp2005-71133
Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::32abd5f536ecbd4b5a8d39f91c7bdd9b
https://doi.org/10.2172/48628
https://doi.org/10.2172/48628