Eric Woolstenhulme - Academia.edu (original) (raw)
Papers by Eric Woolstenhulme
Transactions of the American Nuclear Society, Jul 1, 1999
Since 1997 a variety of reactor fuels have been removed from storage pools, conditioned in a fuel... more Since 1997 a variety of reactor fuels have been removed from storage pools, conditioned in a fuel canning station (FCS), and stored in the dry shielded Irradiated Fuel Storage Facility (IFSF) at the Idaho Nuclear Technology and Engineering Center (INTEC). Problems developed operating the FCS to safely and efficiently dry fuel, to monitor and control important parameters such as fuel temperature, to measure and document the extent of dryness, and to avoid pyrophoricity with some fuels in dry storage. The ways these problems were resolved during startup and hot operation of the FCS are described herein.
The Department of Energy's Idaho National Laboratory, under its programmatic responsibility for m... more The Department of Energy's Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at the University of Florida. With this work completed and in anticipation of other impending conversion projects, INL convened and engaged the project participants in a structured discussion to capture the lessons learned. This lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project team's experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.
The Department of Energy's Idaho National Laboratory, under its programmatic responsibility for m... more The Department of Energy's Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at the Texas A&M University Nuclear Science Center Reactor. With this work completed and in anticipation of other impending conversion projects, INL convened and engaged the project participants in a structured discussion to capture the lessons learned. This lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project team's experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.
Frontiers in Energy Research, Mar 17, 2023
Low-enriched (LEU) U-ZrH fuel, with a 235 U content less than 20% of the total uranium, is being ... more Low-enriched (LEU) U-ZrH fuel, with a 235 U content less than 20% of the total uranium, is being evaluated for possible use in different types of reactors, including space nuclear systems, light water reactors (LWRs) and micro-reactors. As a result, it is beneficial to better understand the macrostructural and microstructural changes that occur in this fuel during irradiation. This paper reports the results of the post irradiation examination of an LEU U-ZrH fuel element (30 wt.% U, <20% 235 U) using neutron radiography, precision gamma scanning, chemical analysis, optical metallography and scanning electron microscopy combined with energy dispersive spectroscopy and wavelength dispersive spectroscopy, where the fuel element was irradiated in a Training, Research, Isotope, General Atomics (TRIGA) reactor. Results of microstructural characterization indicated some dehydriding and cracking of the U-ZrH fuel occurred during irradiation; an axial and radial burnup gradient existed in the fuel during irradiation, as measured by gamma scanning and chemical analysis; negligible microstructural changes transpired during irradiation, based on comparison of irradiated and as-fabricated U-ZrH fuel microstructures; and, negligible, fission product-rich, phases could be resolved in a U-ZrH fuel that was irradiated to a calculated 20% depletion of 235 U.
From a handling perspective, any spent nuclear fuel (SNF) that has lost its original technical an... more From a handling perspective, any spent nuclear fuel (SNF) that has lost its original technical and functional design capabilities with regard to handling and confinement can be considered as damaged. Some SNF was damaged as a result of experimental activities and destructive examinations; incidents during packaging, handling, and transportation; or degradation that has occurred during storage. Some SNF was mechanically destroyed to protect proprietary SNF designs. Examples of damage to the SNF include failed cladding, failed fuel meat, sectioned test specimens, partially reprocessed SNFs, overheated elements, dismantled assemblies, and assemblies with lifting fixtures removed. In spite of the challenges involved with handling and storage of damaged SNF, the SNF has been safely handled and stored for many years at DOE storage facilities. This report summarizes a variety of challenges encountered at DOE facilities during interim storage and handling operations along with strategies and solutions that are planned or were implemented to ameliorate those challenges. A discussion of proposed paths forward for moving damaged and nondamaged SNF from interim storage to final disposition in the geologic repository is also presented.
... Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, PO Box 1625 Idaho Fa... more ... Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, PO Box 1625 Idaho Falls, ID 83415 (United States)]; McCormack, Roger L. [Fluor Hanford Site, Richland, Wash. (United States)]; Sindelar, Robert; Spieker, Timothy [Savannah River National Laboratory ...
Frontiers in Energy Research
Low-enriched (LEU) U-ZrH fuel, with a235U content less than 20% of the total uranium, is being ev... more Low-enriched (LEU) U-ZrH fuel, with a235U content less than 20% of the total uranium, is being evaluated for possible use in different types of reactors, including space nuclear systems, light water reactors (LWRs) and micro-reactors. As a result, it is beneficial to better understand the macrostructural and microstructural changes that occur in this fuel during irradiation. This paper reports the results of the post irradiation examination of an LEU U-ZrH fuel element (30 wt.% U, <20% 235U) using neutron radiography, precision gamma scanning, chemical analysis, optical metallography and scanning electron microscopy combined with energy dispersive spectroscopy and wavelength dispersive spectroscopy, where the fuel element was irradiated in a Training, Research, Isotope, General Atomics (TRIGA) reactor. Results of microstructural characterization indicated some dehydriding and cracking of the U-ZrH fuel occurred during irradiation; an axial and radial burnup gradient existed in th...
Since 1997 a variety of reactor fuels have been removed from storage pools, conditioned in a fuel... more Since 1997 a variety of reactor fuels have been removed from storage pools, conditioned in a fuel canning station (FCS), and stored in the dry shielded Irradiated Fuel Storage Facility (IFSF) at the Idaho Nuclear Technology and Engineering Center (INTEC). Problems developed operating the FCS to safely and efficiently dry fuel, to monitor and control important parameters such as fuel temperature, to measure and document the extent of dryness, and to avoid pyrophoricity with some fuels in dry storage. The ways these problems were resolved during startup and hot operation of the FCS are described herein.
Transactions of the American Nuclear Society - Volume 123, 2020
This report presents the findings of an investigation into high-temperature fuel cladding chemica... more This report presents the findings of an investigation into high-temperature fuel cladding chemical interactions (FCCI) in Training, Research, Isotopes, General Atomics (TRIGA) fuel rods. A TRIGA fuel-rod core or meat is principally composed of uranium (U) particles dispersed in a zirconium-hydride (Zr-H) matrix. The fuel is clad in sealed 304SS or Incoloy 800 tubes. At high temperatures, the fuel will interact with the cladding, resulting in FCCI.
Transactions of the American Nuclear Society - Volume 121, 2019
High-temperature fuel cladding chemical interactions (FCCI) between Training, Research, Isotopes,... more High-temperature fuel cladding chemical interactions (FCCI) between Training, Research, Isotopes, General Atomics (TRIGA) fuel elements and the 304 stainless steel (304SS) are of interest to develop an understanding of the fuel behavior during transient reactor scenarios, such as a loss-of-coolant-accident (LOCA). TRIGA fuels are composed of uranium (U) particles dispersed in a zirconium-hydride (Zr-H) matrix. In the reactor, the fuel is encased in 304SS or Incoloy 800 clad tubes. At high temperatures, the fuel has the potential to interact with the cladding, resulting in FCCI. A number of FCCI can take place in this system. Interactions can be expected between the cladding and the Zr-H matrix, and/or between the cladding and the U-particles. Other interactions may be expected between the Zr-H matrix and the U-particles. Furthermore, the fuel contains erbium-oxide (Er 2 O 3) additions. Interactions can also be expected between the Er 2 O 3 , the cladding, the Zr-H and the U-particles. The overall result is that very complex interactions may take place as a result of fuel and cladding exposures to high temperatures. These interactions must be understood to ensure safe operation of the fuels under normal and transient conditions. This report discusses the characterization of the baseline fuel microstructure in the as-received state (prior to exposure to high temperature), characterization of the fuel after annealing at 950°C for 5, 16, and 24 hours, and the results from diffusion couple experiments carried out at 1000°C for 5 and 24 hours. Emphasis is given to the interaction regions between TRIGA fuels in contact with 304SS and the development of low-melting-temperature phases. Characterization was carried out via scanning electron microscopy (SEM) and transmission electron microscopy (TEM) with sample preparation via focused ion beam in situ lift-out technique.
The RERTR U.S. Domestic Conversion program continues in its support of the Global Treat Reduction... more The RERTR U.S. Domestic Conversion program continues in its support of the Global Treat Reduction Initiative
Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 2006
... Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, PO Box 1625 Idaho Fa... more ... Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, PO Box 1625 Idaho Falls, ID 83415 (United States)]; McCormack, Roger L. [Fluor Hanford Site, Richland, Wash. (United States)]; Sindelar, Robert; Spieker, Timothy [Savannah River National Laboratory ...
Transactions of the American Nuclear Society, Jul 1, 1999
Since 1997 a variety of reactor fuels have been removed from storage pools, conditioned in a fuel... more Since 1997 a variety of reactor fuels have been removed from storage pools, conditioned in a fuel canning station (FCS), and stored in the dry shielded Irradiated Fuel Storage Facility (IFSF) at the Idaho Nuclear Technology and Engineering Center (INTEC). Problems developed operating the FCS to safely and efficiently dry fuel, to monitor and control important parameters such as fuel temperature, to measure and document the extent of dryness, and to avoid pyrophoricity with some fuels in dry storage. The ways these problems were resolved during startup and hot operation of the FCS are described herein.
The Department of Energy's Idaho National Laboratory, under its programmatic responsibility for m... more The Department of Energy's Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at the University of Florida. With this work completed and in anticipation of other impending conversion projects, INL convened and engaged the project participants in a structured discussion to capture the lessons learned. This lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project team's experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.
The Department of Energy's Idaho National Laboratory, under its programmatic responsibility for m... more The Department of Energy's Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at the Texas A&M University Nuclear Science Center Reactor. With this work completed and in anticipation of other impending conversion projects, INL convened and engaged the project participants in a structured discussion to capture the lessons learned. This lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project team's experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.
Frontiers in Energy Research, Mar 17, 2023
Low-enriched (LEU) U-ZrH fuel, with a 235 U content less than 20% of the total uranium, is being ... more Low-enriched (LEU) U-ZrH fuel, with a 235 U content less than 20% of the total uranium, is being evaluated for possible use in different types of reactors, including space nuclear systems, light water reactors (LWRs) and micro-reactors. As a result, it is beneficial to better understand the macrostructural and microstructural changes that occur in this fuel during irradiation. This paper reports the results of the post irradiation examination of an LEU U-ZrH fuel element (30 wt.% U, <20% 235 U) using neutron radiography, precision gamma scanning, chemical analysis, optical metallography and scanning electron microscopy combined with energy dispersive spectroscopy and wavelength dispersive spectroscopy, where the fuel element was irradiated in a Training, Research, Isotope, General Atomics (TRIGA) reactor. Results of microstructural characterization indicated some dehydriding and cracking of the U-ZrH fuel occurred during irradiation; an axial and radial burnup gradient existed in the fuel during irradiation, as measured by gamma scanning and chemical analysis; negligible microstructural changes transpired during irradiation, based on comparison of irradiated and as-fabricated U-ZrH fuel microstructures; and, negligible, fission product-rich, phases could be resolved in a U-ZrH fuel that was irradiated to a calculated 20% depletion of 235 U.
From a handling perspective, any spent nuclear fuel (SNF) that has lost its original technical an... more From a handling perspective, any spent nuclear fuel (SNF) that has lost its original technical and functional design capabilities with regard to handling and confinement can be considered as damaged. Some SNF was damaged as a result of experimental activities and destructive examinations; incidents during packaging, handling, and transportation; or degradation that has occurred during storage. Some SNF was mechanically destroyed to protect proprietary SNF designs. Examples of damage to the SNF include failed cladding, failed fuel meat, sectioned test specimens, partially reprocessed SNFs, overheated elements, dismantled assemblies, and assemblies with lifting fixtures removed. In spite of the challenges involved with handling and storage of damaged SNF, the SNF has been safely handled and stored for many years at DOE storage facilities. This report summarizes a variety of challenges encountered at DOE facilities during interim storage and handling operations along with strategies and solutions that are planned or were implemented to ameliorate those challenges. A discussion of proposed paths forward for moving damaged and nondamaged SNF from interim storage to final disposition in the geologic repository is also presented.
... Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, PO Box 1625 Idaho Fa... more ... Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, PO Box 1625 Idaho Falls, ID 83415 (United States)]; McCormack, Roger L. [Fluor Hanford Site, Richland, Wash. (United States)]; Sindelar, Robert; Spieker, Timothy [Savannah River National Laboratory ...
Frontiers in Energy Research
Low-enriched (LEU) U-ZrH fuel, with a235U content less than 20% of the total uranium, is being ev... more Low-enriched (LEU) U-ZrH fuel, with a235U content less than 20% of the total uranium, is being evaluated for possible use in different types of reactors, including space nuclear systems, light water reactors (LWRs) and micro-reactors. As a result, it is beneficial to better understand the macrostructural and microstructural changes that occur in this fuel during irradiation. This paper reports the results of the post irradiation examination of an LEU U-ZrH fuel element (30 wt.% U, <20% 235U) using neutron radiography, precision gamma scanning, chemical analysis, optical metallography and scanning electron microscopy combined with energy dispersive spectroscopy and wavelength dispersive spectroscopy, where the fuel element was irradiated in a Training, Research, Isotope, General Atomics (TRIGA) reactor. Results of microstructural characterization indicated some dehydriding and cracking of the U-ZrH fuel occurred during irradiation; an axial and radial burnup gradient existed in th...
Since 1997 a variety of reactor fuels have been removed from storage pools, conditioned in a fuel... more Since 1997 a variety of reactor fuels have been removed from storage pools, conditioned in a fuel canning station (FCS), and stored in the dry shielded Irradiated Fuel Storage Facility (IFSF) at the Idaho Nuclear Technology and Engineering Center (INTEC). Problems developed operating the FCS to safely and efficiently dry fuel, to monitor and control important parameters such as fuel temperature, to measure and document the extent of dryness, and to avoid pyrophoricity with some fuels in dry storage. The ways these problems were resolved during startup and hot operation of the FCS are described herein.
Transactions of the American Nuclear Society - Volume 123, 2020
This report presents the findings of an investigation into high-temperature fuel cladding chemica... more This report presents the findings of an investigation into high-temperature fuel cladding chemical interactions (FCCI) in Training, Research, Isotopes, General Atomics (TRIGA) fuel rods. A TRIGA fuel-rod core or meat is principally composed of uranium (U) particles dispersed in a zirconium-hydride (Zr-H) matrix. The fuel is clad in sealed 304SS or Incoloy 800 tubes. At high temperatures, the fuel will interact with the cladding, resulting in FCCI.
Transactions of the American Nuclear Society - Volume 121, 2019
High-temperature fuel cladding chemical interactions (FCCI) between Training, Research, Isotopes,... more High-temperature fuel cladding chemical interactions (FCCI) between Training, Research, Isotopes, General Atomics (TRIGA) fuel elements and the 304 stainless steel (304SS) are of interest to develop an understanding of the fuel behavior during transient reactor scenarios, such as a loss-of-coolant-accident (LOCA). TRIGA fuels are composed of uranium (U) particles dispersed in a zirconium-hydride (Zr-H) matrix. In the reactor, the fuel is encased in 304SS or Incoloy 800 clad tubes. At high temperatures, the fuel has the potential to interact with the cladding, resulting in FCCI. A number of FCCI can take place in this system. Interactions can be expected between the cladding and the Zr-H matrix, and/or between the cladding and the U-particles. Other interactions may be expected between the Zr-H matrix and the U-particles. Furthermore, the fuel contains erbium-oxide (Er 2 O 3) additions. Interactions can also be expected between the Er 2 O 3 , the cladding, the Zr-H and the U-particles. The overall result is that very complex interactions may take place as a result of fuel and cladding exposures to high temperatures. These interactions must be understood to ensure safe operation of the fuels under normal and transient conditions. This report discusses the characterization of the baseline fuel microstructure in the as-received state (prior to exposure to high temperature), characterization of the fuel after annealing at 950°C for 5, 16, and 24 hours, and the results from diffusion couple experiments carried out at 1000°C for 5 and 24 hours. Emphasis is given to the interaction regions between TRIGA fuels in contact with 304SS and the development of low-melting-temperature phases. Characterization was carried out via scanning electron microscopy (SEM) and transmission electron microscopy (TEM) with sample preparation via focused ion beam in situ lift-out technique.
The RERTR U.S. Domestic Conversion program continues in its support of the Global Treat Reduction... more The RERTR U.S. Domestic Conversion program continues in its support of the Global Treat Reduction Initiative
Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 2006
... Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, PO Box 1625 Idaho Fa... more ... Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, PO Box 1625 Idaho Falls, ID 83415 (United States)]; McCormack, Roger L. [Fluor Hanford Site, Richland, Wash. (United States)]; Sindelar, Robert; Spieker, Timothy [Savannah River National Laboratory ...