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Rebecca E. Smith

Bio: Rebecca E. Smith is an academic researcher. The author has contributed to research in topics: Nuclear fuel cycle & Spent nuclear fuel. The author has an hindex of 1, co-authored 1 publications receiving 6 citations.

Papers
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01 Sep 2011
TL;DR: In this paper, the authors developed a bibliography to assess what issues associated with fuel drying have been identified, to consider where concerns have been satisfactorily addressed, and to recommend where additional research would offer the most value to the commercial industry and the U. S. Department of Energy.
Abstract: Internationally, the nuclear industry is represented by both commercial utilities and research institutions. Over the past two decades many of these entities have had to relocate inventories of spent nuclear fuel from underwater storage to dry storage. These efforts were primarily prompted by two factors: insufficient storage capacity (potentially precipitated by an open-ended nuclear fuel cycle) or deteriorating quality of existing underwater facilities. The intent of developing this bibliography is to assess what issues associated with fuel drying have been identified, to consider where concerns have been satisfactorily addressed, and to recommend where additional research would offer the most value to the commercial industry and the U. S. Department of Energy.

6 citations


Cited by
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Journal ArticleDOI
TL;DR: In this paper, the effect of water vapor on the UO2 surface as a function of temperature was studied in situ inside a high pressure chamber attached to the X-Ray Photoelectron Spectroscopy (XPS) instrument.

6 citations

01 Jan 1971
TL;DR: In this paper, the mechanical aspects of fuel cladding, especially the zircaloys' performance requirements under BWR and PWR conditions, are discussed, which are not greatly dissimilar.
Abstract: This lecture is concerned with the mechanical aspects of fuel cladding, especially the zircaloys', and is related to performance requirements under BWR and PWR conditions, which, in this area, are not greatly dissimilar.

3 citations

Journal ArticleDOI
TL;DR: In this article, the influence of epsilon particles and metallic precipitates, simulated through the deposition of Pd nanoparticles on non-irradiated UO2, on the oxidation of the spent nuclear fuel (SNF).
Abstract: This work studies the influence of epsilon particles and metallic precipitates, simulated through the deposition of Pd nanoparticles on non-irradiated UO2, on the oxidation of the spent nuclear fuel (SNF). The presence of Pd nanoparticles favored the reduction by hydrogen of oxidized uranium phases located on the UO2 surface, decreased the oxidation of the UO2 by H2O in the absence of hydrogen, and, in the presence of hydrogen and water vapor, no oxidation of the UO2 by water was detected, contrasting experiments without Pd nanoparticles.

3 citations

ReportDOI
04 Aug 1998
TL;DR: In this paper, the authors evaluate the safety functions of the Multi-Canister Overpack (MCO) and identify any additional NRC requirements needed, in combination with the existing and applicable DOE requirements, to establish nuclear safety equivalency for the MCO.
Abstract: The US Department of Energy (DOE), established in the K Basin Spent Nuclear Fuel Project Regulatory Policy, dated August 4, 1995 (hereafter referred to as the Policy), the requirement for new Spent Nuclear Fuel (SNF) Project facilities to achieve nuclear safety equivalency to comparable US Nuclear Regulatory Commission (NRC)-licensed facilities. For activities other than during transport, when the Multi-Canister Overpack (MCO) is used and resides in the Canister Storage Building (CSB), Cold Vacuum Drying (CVD) facility or Hot Conditioning System, additional NRC requirements will also apply to the MCO based on the safety functions it performs and its interfaces with the SNF Project facilities. An evaluation was performed in consideration of the MCO safety functions to identify any additional NRC requirements needed, in combination with the existing and applicable DOE requirements, to establish nuclear safety equivalency for the MCO. The background, basic safety issues and general comparison of NRC and DOE requirements for the SNF Project are presented in WHC-SD-SNF-DB-002.

1 citations