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Interim Storage, Environmental Justice, and Generational Equity

Interim Storage, Environmental Justice, and Generational Equity

Author(s)
Leigh, C.D. ,
Dotson, L.J.
Publication Date

With the termination of the Yucca Mountain project, which was proposed to be our nation’s first repository for the disposal of military and civilian spent nuclear fuel and high-level radioactive waste, the future of nuclear waste management and disposal in this country became increasingly uncertain. Interim storage has been advocated by many as a temporary solution while a permanent solution is studied for potentially several more decades to come.

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

Data Qualification Report: Mineralogy Data for Use on the Yucca Mountain Project

Data Qualification Report: Mineralogy Data for Use on the Yucca Mountain Project

Author(s)
T.L. Steinborn
Publication Date
This DQR uses the technical assessment methods according to Attachment 2 of AP-SIII.2Q, Rev. 0, ICN 3, to qualify DTN LADB831321AN98.002. The data addressed in this DQR have been cited in CRWMS M&O (2000b) to support the Site Recommendation in determining the suitability of Yucca Mountain as a repository for high level nuclear waste. CRWMS M&O (2000b) refers to mineral analyses that are unqualified.
yucca mountain repository license application data qualification tdr-nbs-hs-000005 minerals xrd mineral concentration

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

Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update

Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update

Author(s)
U.S. Nuclear Waste Technical Review Board
Publication Date

In October 2009, the U.S. Nuclear Waste Technical Review Board (Board or NWTRB) published Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel.  For each of the 13 national programs studied, the report catalogued 15 institutional arrangements that had been set in place and 15 technical approaches that had been taken to design repository systems for the long-term management of high-activity radioactive waste.

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