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Uncertainty quantification methodologies development for storage and trans- portation of used nuclear fuel: Pilot study on stress corrosion cracking of canister welds

Uncertainty quantification methodologies development for storage and trans- portation of used nuclear fuel: Pilot study on stress corrosion cracking of canister welds

Author(s)
Remi Dingreville ,
Cedric Sallaberry ,
Charles Bryan ,
Christine Stockman ,
Harold Adkins ,
Mark Sutton
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.

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.

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.

Environmental Risk Characterization Work Plan Yankee Nuclear Power Station Rowe, Massachusetts

Environmental Risk Characterization Work Plan Yankee Nuclear Power Station Rowe, Massachusetts

Author(s)
Gradient Corporation
Publication Date
This document presents a work plan for performing an environmental risk assessment to support the environmental site closure underway at the Yankee Nuclear Power Station (YNPS). A work plan for the human health risk assessment was submitted as a separate document (Gradient, 2006). The YNPS is located in the town of Rowe, situated in northwestern Massachusetts along the Deerfield River adjacent to Sherman Dam (Figure 1-1).
ynps enviornmental risk characterization work plan

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Author(s)
Mueller, D. E. ,
Wagner, J. C.
Publication Date
The responsible use of calculational methods in nuclear criticality safety includes a determination of bias and bias uncertainty that may exist between the calculated results and reality. Such biases exist due to approximations used to model the real world, uncertainties in nuclear data, and approximations associated with the calculational method (e.g., Monte Carlo method). The bias and bias uncertainty are typically determined by using the modeling approximations, nuclear data, and calculational method to model well-known, usually critical, systems.
burnup credit criticality analysis iaea-tecdoc-1547 iaea sensitivity analysis

OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

Author(s)
Nouri, A.
Publication Date
The OECD/NEA “Burn-up Credit Criticality Benchmark” working group has studied the effect of axial burn-up profile on the criticality of a realistic PWR spent fuel transport cask (Phase II-B). The final results of this benchmark are presented and analysed in this report. Nine basic cases and two additional accident configurations were considered with the following varying parameters: burn-up (0 GWd/t for fresh fuel, 30 and 50 GWd/t), fuel composition (actinides only and actinides with fifteen fission products), axial burn-up discretisation (1 or 9 zones).
criticality pwr fuel transport cask end effect source convergence burnup axial burnup profile
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