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The effect of low dose-rate irradiation on the microstructure of 304 stainless steel.

Description: Changes in mechanical and corrosion properties caused by the development of radiation-induced microstructure have relevance to the aging and lifetime extension of light water reactors (LWR's). However, much of the current data related to microstructural development in irradiated metals are generated from studies carried out at much higher dose-rates than encountered in LWR's. An opportunity exists to study the influence of low dose-rate irradiation on microstructural development for a variety o… more
Date: December 2, 1998
Creator: Cole, J. I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Post-irradiation deformation characteristics of heavy-ion irradiated 304L SS

Description: Post-irradiation deformation behavior in Ni-ion-irradiated 304L stainless steel (SS) is examined as a function of radiation dose and deformation temperature. For similar strain levels, specimens exhibit a transition from dislocation slip to deformation-induced twinning at 25C with increasing radiation dose. At 288C twinning is no longer observed and highly localized slip occurs by the formation of narrow ``channels`` containing a reduced defect density. The observations are discussed in terms o… more
Date: June 1, 1994
Creator: Cole, J. I. & Bruemmer, S. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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AN EVALUATION OF POTENTIAL LINER MATERIALS FOR ELIMINATING FCCI IN IRRADIATED METALLIC NUCLEAR FUEL ELEMENTS

Description: Metallic nuclear fuels are being looked at as part of the Global Nuclear Energy Program for transmuting longlive transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products. In order to optimize the performance of these fuels, the concept of using liners to eliminate the fuel/cladding chemical interactions that can occur during irradiation of a fuel element has been investigated. The potential liner materials Zr and V have been tested using solid-solid diff… more
Date: September 1, 2007
Creator: Keiser, D. D. & Cole, J. I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Use of Friction Stir Welding and Friction Stir Processing for Advanced Nuclear Fuels and Materials Joining Applications

Description: Application of the latest developments in materials technology may greatly aid in the successful pursuit of next generation reactor and transmutation technologies. One such area where significant progress is needed is joining of advanced fuels and materials. Rotary friction welding, also referred to as friction stir welding (FSW), has shown great promise as a method for joining traditionally difficult to join materials such as aluminum alloys. This relatively new technology, first developed in … more
Date: June 1, 2006
Creator: Cole, J. I. & Jue, J. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Microstructural Characterization of Cast Metallic Transmutation Fuels

Description: As part of the Global Nuclear Energy Partnership (GNEP) and the Advanced Fuel Cycle Initiative (AFCI), the US Department of Energy (DOE) is participating in an international collaboration to irradiate prototypic actinide-bearing transmutation fuels in the French Phenix fast reactor (FUTURIX-FTA experiment). The INL has contributed to this experiment by fabricating and characterizing two compositions of metallic fuel; a non-fertile 48Pu-12Am-40Zr fuel and a low-fertile 35U-29Pu-4Am-2Np-30Zr fuel… more
Date: September 1, 2007
Creator: Cole, J. I.; Keiser, D. D. & Kennedy, J. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Temperature and strain-rate effects on deformation mechanisms in irradiated stainless steel

Description: Analysis of the deformation microstructures in ion-irradiated stainless steel shows twinning to be the predominant deformation mode at room temperature. Dislocation channelling also occurs under slow strain rate conditions. Stresses required for twinning were calculated by the model of Venables and are compatible with observed yield stresses in neutron-irradiated material if loops are the principal twin source. Computation of the expected radiation hardening from the defect structure, based on … more
Date: November 1, 1994
Creator: Brimhall, J. L.; Cole, J. I.; Vetrano, J. S. & Bruemmer, S. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radiation-induced segregation and the relationship to physical properties in irradiated austenitic alloys.

Description: Radiation-induced changes in composition are studied because these changes can degrade failure of materials irradiated in nuclear reactors. In this work, the effect of alloy composition on radiation-induced segregation, hardening, and void swelling is presented. Five alloys, Fe-18Cr-8Ni, Fe-16Cr-13Ni, Fe-18Cr-40Ni, Fe-16Cr-13Ni+Mo, and Fe-16Cr-13Ni+Mo+P (all compositions in wt. %), were irradiated with 3.2 MeV protons at 400 C to a dose of 0.5 displacements per atom. The change in grain boundar… more
Date: June 5, 2002
Creator: Allen, T. R.; Cole, J. I.; Was, G. S. & Kenik, E. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Irradiation effects on the electrochemistry and corrosion resistance of stainless steel

Description: Nickel-ion irradiation at 500{degrees}C is shown to have a strong effect on the surface electrochemistry and intergranular corrosion of stainless steel. Measured current densities in a 1N H{sub 2}SO{sub 4} solution at room temperature are increased at active-passive, passive, and transpassive potentials. Irradiation effects on the current decay behavior and susceptibility to intergranular corrosion were similar for a microcrystalline, fine-grained stainless alloy and for a very large-grained st… more
Date: April 1, 1992
Creator: Bruemmer, S. M.; Arey, B. W.; Windisch, C. F., Jr. & Cole, J. I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Irradiation effects on the electrochemistry and corrosion resistance of stainless steel

Description: Nickel-ion irradiation at 500{degrees}C is shown to have a strong effect on the surface electrochemistry and intergranular corrosion of stainless steel. Measured current densities in a 1N H{sub 2}SO{sub 4} solution at room temperature are increased at active-passive, passive, and transpassive potentials. Irradiation effects on the current decay behavior and susceptibility to intergranular corrosion were similar for a microcrystalline, fine-grained stainless alloy and for a very large-grained st… more
Date: April 1, 1992
Creator: Bruemmer, S. M.; Arey, B. W.; Windisch, C. F. Jr. & Cole, J. I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Developing improved structural materials using proton irradiation as a rapid analysis tool.

Description: The overall goal of the project is to develop austenitic stainless steel structural materials with enhanced radiation resistance. For this project, the term radiation resistance is being used to describe resistance to dimensional changes caused by void swelling and resistance to material failures caused by irradiation assisted stress corrosion cracking (IASCC). IASCC has been linked to both hardening and changes in grain boundary composition during irradiation. To achieve such enhanced radiatio… more
Date: October 7, 2003
Creator: Allen, T. R.; Cole, J. I.; Dropek, R.; Gan, J. & Was, G. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mechanical properties of 20% cold-worked 316 stainless steel irradiated at low dose rate.

Description: To assess the effects of long-term, low-dose-rate neutron exposure on mechanical strength and ductility, tensile properties were measured on irradiated 20% cold-worked Type 316 stainless steel. Samples were prepared from reactor core components retrieved from the EBR-II reactor following final shutdown. Sample locations were chosen to cover a dose range of 1-47 dpa at temperatures from 371-385 C and dose rates from 0.8-2.8 x 10{sup -7} dpa/s. These dose rates are about one order of magnitude lo… more
Date: December 11, 2001
Creator: Allen, T. R.; Tsai, H.; Cole, J. I.; Ohta, J.; Dohi, K. & Kusanagi, H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Properties of 20% cold-worked 316 stainless steel irradiated at low dose rate.

Description: To assess the effects of long-term, low-dose-rate neutron exposure, tensile, hardness, and fracture properties were measured and microstructural characterization performed on irradiated 20% cold-worked Type 316 stainless steel. Samples were prepared from reactor core components retrieved from the EBR-II reactor following final shutdown. Sample locations were chosen to cover a dose range of 1-56 dpa at temperatures from 371-390 C and dose rates from 0.8-3.3 x 10{sup -7} dpa/s. Irradiation caused… more
Date: June 5, 2002
Creator: Allen, T. R.; Tsai, H.; Cole, J. I.; Ohta, J.; Dohi, K. & Kusanagi, H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radiation hardening effects on localized deformation and stress corrosion cracking of stainless steels

Description: Radiation hardening in austenitic stainless steels modifies deformation characteristics and correlate well with increased susceptibility to intergranular stress corrosion cracking (IGSCC). Available data on neutron-irradiated materials have been analyzed and correlations developed between fluence, yield strength, and cracking susceptibility in high-temperature water environments. Large heat-to-heat differences in critical fluence (0.2 to 2.5 {times} 10{sup 21} n/cm{sup 2}) for IGSCC are documen… more
Date: August 1, 1993
Creator: Bruemmer, S. M.; Cole, J. I.; Brimhall, J. L.; Carter, R. D. & Was, G. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The influence of pre-irradiation heat treatments on thermal non-equilibrium and radiation-induced segregation behavior in model austenitic stainless steel alloys.

Description: The effect of pre-irradiation heat treatments on thermal non-equilibrium grain boundary segregation (TNES) and subsequent radiation-induced grain boundary segregation (RIS) is studied in a series of model austenitic stainless steels. The alloys used for this study are based on AISI 316 stainless steel and have the following nominal compositions: Fe-16Cr-13Ni-1.25Mn (base 316), Fe-16Cr-13Ni-1.25Mn-2.0Mo (316 + Mo) and Fe-16Cr-13Ni-1.25Mn-2.0Mo-0.07P (316 + Mo + P). Samples were heat treated at t… more
Date: July 29, 2002
Creator: Cole, J. I.; Allen, T. R.; Was, G. S.; Dropek, R. B. & Kenik, E. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear energy plant optimization (NEPO) final scientific/technical report

Description: The overall objective of this 3 year research program has been to support the aging management programs for LWR reactors through the extended 60-year lifetimes by adding to the knowledge base of irradiation-induced effects on the mechanical properties and cracking resistance of stainless steel (SS) core components. Over the course of this project, efforts have focused on enhancing the understanding of the link between deformation and fracture behavior in work-hardened and irradiated stainless s… more
Date: February 2, 2004
Creator: Cole, J. I.; Daum, R. S.; Tsai, H.; Porter, D. L.; Allen, T. R. & Wirth, B. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The effect of low dose rate irradiation on the tensile properties and microstructure of austenitic stainless steel.

Description: To assess the effects of long-term, low-dose-rate neutron exposure on mechanical strength and ductility, tensile properties were measured on 12% and 20% cold-worked Type 316 stainless steel. Samples were prepared from reactor core components retrieved from the EBR-II reactor following final shutdown. Sample locations were chosen to cover a dose range of 1-56 dpa at temperatures from 371-440 C and dose rates from 0.5-5.8 x10{sup -7} dpa/s. These dose rates are approximately an order of magnitude… more
Date: September 17, 2002
Creator: Allen, T. R.; Tsai, H.; Cole, J. I.; Yoshitake, T.; Akasaka, N.; Donomae, T. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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