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Displaying 76 - 95 of 95

Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems

Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems

Author(s)
Abdelhalim Alsaed ,
James Blink ,
Mark Nutt ,
Brian Gutherman ,
Bruce Balkcom Bevard ,
Rob L. Howard ,
Joshua J. Jarrell ,
John M. Scaglione ,
John C. Wagner ,
S. J. Maheras ,
C. L. Bryan ,
Ernest Hardin ,
Anastesia Ilgen ,
Elena Kalina
Publication Date
Abstract does not exist for this document.

Socio-technical multi-criteria evaluation of long-term spent nuclear fuel management strategies: A framework and method

Socio-technical multi-criteria evaluation of long-term spent nuclear fuel management strategies: A framework and method

Author(s)
Diaz-Maurin, François ,
Yu, Jerold ,
Ewing, Rodney C.
Publication Date

In the absence of a federal geologic repository or consolidated, interim storage in the United States, commercial spent fuel will remain stranded at some 75 sites across the country. Currently, these include 18 “orphaned sites” where spent fuel has been left at decommissioned reactor sites.

Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

Author(s)
Broadhead, B. L. ,
DeHart, M. D. ,
Ryman, J. C. ,
Tang, J. S. ,
Parks, C. V.
Publication Date
The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final repository site.
burnup credit spent fuel transport lwr ornl/tm-12742 nuclide used fuel

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3-Surry Unit 1 Cycle 2

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3-Surry Unit 1 Cycle 2

Author(s)
Hermann, O. W. ,
Bowman, S. M.
Publication Date
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor criticality safety analyses be validated against experimental measurements. If credit for the negative reactivity of the depleted (or spent) fuel isotopics is desired, it is necessary to benchmark computational methods against spent fuel critical configurations.
burnup credit scale pwr ornl/tm-12294/v3 surry
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