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Dive into the research topics where Ken B. Sorenson is active.

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Featured researches published by Ken B. Sorenson.


Nuclear Engineering and Technology | 2013

MAKING THE CASE FOR SAFE STORAGE OF USED NUCLEAR FUEL FOR EXTENDED PERIODS OF TIME: COMBINING NEAR-TERM EXPERIMENTS AND ANALYSES WITH LONGER-TERM CONFIRMATORY DEMONSTRATIONS

Ken B. Sorenson; Brady D. Hanson

The need for extended storage of used nuclear fuel is increasing globally as disposition schedules for used fuel are pushed further into the future. This is creating a situation where dry storage of used fuel may need to be extended beyond normal regulatory licensing periods. While it is generally accepted that used fuel in dry storage will remain in a safe condition, there is little data that demonstrate used fuel performance in dry storage environments for long periods of time. This is especially true for high burnup used fuel. This paper discusses a technical approach that defines a process that develops the technical basis for demonstrating the safety of used fuel over extended periods of time.


Nuclear Engineering and Technology | 2011

EXTENDED DRY STORAGE OF USED NUCLEAR FUEL: TECHNICAL ISSUES: A USA PERSPECTIVE

Paul E. McConnell; Brady D. Hanson; Moo Lee; Ken B. Sorenson

Used nuclear fuel will likely be stored dry for extended periods of time in the USA. Until a final disposition pathway is chosen, the storage periods will almost definitely be longer than were originally intended. The ability of the important-tosafety structures, systems, and components (SSCs) to continue to meet storage and transport safety functions over extended times must be determined. It must be assured that there is no significant degradation of the fuel or dry cask storage systems. Also, it is projected that the maximum discharge burnups of the used nuclear fuel will increase. Thus, it is necessary to obtain data on high burnup fuel to demonstrate that the used nuclear fuel remains intact after extended storage. An evaluation was performed to determine the conditions that may lead to failure of dry storage SSCs. This paper documents the initial technical gap analysis performed to identify data and modeling needs to develop the desired technical bases to ensure the safety functions of dry stored fuel.


Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management | 2013

Overview of the United States Department of Energy’s Used Fuel Disposition Research and Development Campaign

Mark Nutt; Peter N. Swift; Jens T. Birkholzer; William Boyle; Timothy Gunter; Ned Larson; Robert J. MacKinnon; Kevin McMahon; Ken B. Sorenson

The United States Department of Energy (US DOE) is conducting research and development (R&D) activities within the Used Fuel Disposition Campaign (UFDC) to support storage, transportation, and disposal of used nuclear fuel (UNF) and wastes generated by existing and future nuclear fuel cycles. R&D activities are ongoing at nine national laboratories, and are divided into two major topical areas: (1) storage and transportation research, and (2) disposal research. Storage R&D focuses on closing technical gaps related to extended storage of UNF. For example, uncertainties remain regarding high-burnup nuclear fuel cladding performance following possible hydride reorientation and creep deformation, and also regarding long-term canister integrity. Transportation R&D focuses on ensuring transportability of UNF following extended storage, addressing data gaps regarding nuclear fuel integrity, retrievability, and demonstration of subcriticality. Disposal R&D focuses on identifying multiple viable geologic disposal options and addressing technical challenges for generic disposal concepts in various host media (e.g., mined repositories in salt, clay/shale, and granitic rocks, and deep borehole disposal in crystalline rock). R&D will transition to site-specific challenges as national policy advances. R&D goals at this stage are to increase confidence in the robustness of generic disposal concepts, to reduce generic sources of uncertainty that may impact the viability of disposal concepts, and to develop science and engineering tools that will support the selection, characterization, and ultimately licensing of a repository. The US DOE has also initiated activities that can be conducted within the constraints of the Nuclear Waste Policy Act to facilitate the development of an interim storage facility and supporting transportation infrastructure.Copyright


Archive | 2013

Review of NDE Methods for Detection and Monitoring of Atmospheric SCC in Welded Canisters for the Storage of Used Nuclear Fuel

Ryan M. Meyer; Allan F. Pardini; Brady D. Hanson; Ken B. Sorenson

Dry cask storage systems (DCSSs) for used nuclear fuel (UNF) were originally envisioned for storage periods of short duration (~ a few decades). However, uncertainty challenges the opening of a permanent repository for UNF implying that UNF will need to remain in dry storage for much longer durations than originally envisioned (possibly for centuries). Thus, aging degradation of DCSSs becomes an issue that may not have been sufficiently considered in the design phase and that can challenge the efficacy of very long-term storage of UNF. A particular aging degradation concern is atmospheric stress corrosion cracking (SCC) of DCSSs located in marine environments. In this report, several nondestructive (NDE) methods are evaluated with respect to their potential for effective monitoring of atmospheric SCC in welded canisters of DCSSs. Several of the methods are selected for evaluation based on their usage for in-service inspection applications in the nuclear power industry. The technologies considered include bulk ultrasonic techniques, acoustic emission, visual techniques, eddy current, and guided ultrasonic waves.


Nuclear Technology | 1993

An evaluation of the use of depleted uranium as a structural component for transport casks

Paul E. McConnell; Richard Salzbrenner; Gerald William Wellman; Ken B. Sorenson

Depleted uranium (DU) alloys are currently used for gamma-ray shielding in casks and as shielding blocks. For the transport cask application, a significant weight and dimensional penalty exists when using the DU solely for shielding. If credit could be taken for the structural use of the DU for containment in a transport cask, greater payloads may be realized. Mechanical property measurements of several uranium alloys and finite element analyses of prototype transport casks assumed to be constructed, in part, from selected uranium materials were performed to evaluate the potential for the use of DU alloys for cask containment. These data and analyses support the concept of the use of DU alloys for the containment function even under hypothetical accident conditions. A conclusion is that the properties of certain DU alloys are therefore sufficient to warrant further consideration of the material for this purpose.


Archive | 2014

Update of the used fuel disposition Campaign Implementation Plan

Jens T. Birkholzer; Robert J. MacKinnon; Kevin McMahon; Sylvia J. Saltzstein; Ken B. Sorenson; Peter N. Swift

This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign (UFDC) supports achievement of the overarching mission and objectives of the Department of Energy Office of Nuclear Energy Fuel Cycle Technologies Program The implementation plan begins with the assumption of target dates that are set out in the January 2013 DOE Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (http://energy.gov/downloads/strategy-management-and-disposal-used-nuclear-fuel-and-high-level-radioactive-waste). These target dates and goals are summarized in section III. This implementation plan will be maintained as a living document and will be updated as needed in response to progress in the Used Fuel Disposition Campaign and the Fuel Cycle Technologies Program.


MRS Proceedings | 2010

Fuel Cycle Research and Development Program, Used Fuel Disposition Campaign Objective, Mission, Plans, and Activity Status

William Mark Nutt; Mark Peters; Peter N. Swift; Kevin McMahon; Ken B. Sorenson; Patrick Schwab

The safe management and disposition of used nuclear fuel and/or high level nuclear waste is a fundamental aspect of the nuclear fuel cycle. The United States currently utilizes a once-through fuel cycle where used nuclear fuel is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. However, a decision not to use the proposed Yucca Mountain Repository will result in longer interim storage at reactor sites than previously planned. In addition, alternatives to the once-through fuel cycle are being considered and a variety of options are being explored under the U.S. Department of Energys Fuel Cycle Research and Development Program. These two factors lead to the need to develop a credible strategy for managing radioactive wastes from any future nuclear fuel cycle in order to provide acceptable disposition pathways for all wastes regardless of transmutation system technology, fuel reprocessing scheme(s), and/or the selected fuel cycle. These disposition paths will involve both the storing of radioactive material for some period of time and the ultimate disposal of radioactive waste. To address the challenges associated with waste management, the DOE Office of Nuclear Energy established the Used Fuel Disposition Campaign within its Fuel Cycle Research and Development Program in the summer of 2009. The mission of the Used Fuel Disposition Campaign is to identify alternatives and conduct scientific research and technology development to enable storage and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The near-and long-term objectives of the Fuel Cycle Research and Development Program and its Used Fuel Disposition Campaign are presented.


International Journal of Radioactive Materials Transport | 2001

Test Facilities for Radioactive Materials Transport Packages at Sandia National Laboratories, USA

Ken B. Sorenson; D. J. Ammerman; W. L. Uncapher

Abstract Compliance with regulatory requirements for normal and hypothetical accident environments can be demonstrated by testing packages to transport radioactive materials. A comprehensive testing capability has been developed by the US Department of Energy at Sandia National Laboratories to simulate the required test conditions and provide response data. Several of the major test facilities available to support testing of radioactive material packages are described in this paper.


Archive | 2012

Gap Analysis to Support Extended Storage of Used Nuclear Fuel, Rev. 0

Brady D. Hanson; Halim Alsaed; Christine Stockman; David George Enos; Ryan M. Meyer; Ken B. Sorenson


Archive | 2007

Decommissioning of the Iraq former nuclear complex

Mohammed Abbas; Tuama Helou; Bushra Ahmead; Mousa Al-Atia; Mowaffak Al-Mubarak; Jeffrey J. Danneels; John Russell Cochran; Ken B. Sorenson; Roger Coates

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Paul E. McConnell

Sandia National Laboratories

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Sylvia J. Saltzstein

Sandia National Laboratories

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Brady D. Hanson

Pacific Northwest National Laboratory

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Kevin McMahon

Sandia National Laboratories

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Peter N. Swift

Sandia National Laboratories

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Richard Salzbrenner

Sandia National Laboratories

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Jens T. Birkholzer

Lawrence Berkeley National Laboratory

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Ned Larson

United States Department of Energy

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Robert J. MacKinnon

Sandia National Laboratories

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