The Accelerator Production of Tritium Materials Test Program

Maloy, Stuart A.; Sommer, W.F.; James, Michael R.; Romero, Tobias J.; López, Manuel Rodríguez; Zimmermann, Eugene R.; Ledbetter, J.M.

doi:10.13182/nt00-a3132

Cited by 8 publications

(10 citation statements)

References 5 publications

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“…The samples were irradiated to doses up to 23 dpa in sealed, water cooled metal containers [10]. The irradiation time was $6 months and the temperature ranged from 30 to 90°C.…”

Section: Methodsmentioning

confidence: 99%

Oxygen effects on irradiated tantalum alloys

Hosemann

Maloy

Greco

et al. 2009

Journal of Nuclear Materials

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“…The samples were irradiated to doses up to 23 dpa in sealed, water cooled metal containers [10]. The irradiation time was $6 months and the temperature ranged from 30 to 90°C.…”

Section: Methodsmentioning

confidence: 99%

Oxygen effects on irradiated tantalum alloys

Hosemann

Maloy

Greco

et al. 2009

Journal of Nuclear Materials

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“…The elemental composition (balance Fe) of the Mod 9Cr-1Mo (heat 10148 from ORNL) was 0.089C, 0.47Mn, 0.021P, 0.28Si, 0.16Ni, 9.24Cr, 0.96Mo, 0.21V, 0.054Nb, 0.08Co, 0.035N and that of 316L irradiated at PSI was 17.17Cr, 12.24Ni, 2.31Mo, 1.75Mn, 0.077Co, 0.07Cu, 0.019C, 0.35Si, 0.02P, 0.073N while the heat of 316L irradiated at LANL was 17.26Cr, 12.16Ni, 2.57Mo, 1.75Mn, 0.26Cu, 0.019C, 0.65Si, 0.022P, 0.006S. Irradiations at LANL were performed using the Los Alamos Radiation Effects Facility (LASREF) located at the end of the 800 MeV/ 1 mA proton beam [2]. These specimens were irradiated in the form of 2 mm · 8 mm · 0.25 mm thick three point bend specimens to a dose of 9 dpa at an irradiation temperature of 70°C.…”

Section: Methodsmentioning

confidence: 99%

The high temperature three point bend testing of proton irradiated 316L stainless steel and Mod 9Cr–1Mo

Maloy¹,

Zubelewicz²,

Romero³

et al. 2005

Journal of Nuclear Materials

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“…For the present tensile testing, eight SS-3 tensile specimens were irradiated at two different positions in Tube 4 of Insert 17A, an in-beam position of the LANSCE-APT irradiation setup [11][12][13]. In the irradiation experiment, specimens were irradiated with a beam of 800 MeV protons at an average current of 1mA and with spallation neutrons [14,15] emitted from a tungsten target.…”

Section: Experiments and Analysesmentioning

confidence: 99%

“…He and H productions were in the range of 40 to 200 appm and 200 to 1600 appm, respectively. Irradiation temperatures were in the range 30 to 100 o C. These irradiation conditions are summarized in Table 2, and additional information on the LANSCE-APT experiment is given in previous reports [11,13].…”

Section: Experiments and Analysesmentioning

confidence: 99%

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Temperature effects on the mechanical properties of candidate SNS target container materials after proton and neutron irradiation

Byun

Farrell

Lee

et al. 2002

Journal of Nuclear Materials

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This report presents the tensile properties of EC316LN austenitic stainless steel and 9Cr-2WVTa ferritic/martensitic steel after 800 MeV proton and spallation neutron irradiation to doses in the range 0.54 to 2.53 dpa. Irradiation temperatures were in the range 30 to 100°C. Tensile testing was performed at room temperature (20°C) and 164°C to study the effects of test temperature on the tensile properties. Test materials displayed significant radiation-induced hardening and loss of ductility due to irradiation. The EC316LN stainless steel maintained notable strain-hardening capability after irradiation, while the 9Cr-2WVTa ferritic/martensitic steel posted negative strain hardening. In the EC316LN stainless steel, increasing the test temperature from 20°C to 164°C decreased the strength by 13 to 18% and the ductility by 8 to 36%. The tensile data for the EC316LN stainless steel irradiated in spallation conditions were in line with the values in a database for 316 stainless steels for doses up to 1 dpa irradiated in fission reactors at temperatures below 200 o C. However, extra strengthening induced by helium and hydrogen contents is evident in some specimens irradiated to above about 1 dpa. The effect of test temperature for the 9Cr-2WVTa ferritic/martensitic steel was less significant than for the EC316LN stainless steel.In addition, strain-hardening behaviors were analyzed for EC316LN and 316L stainless steels. The strain-hardening rate of the 316 stainless steels was largely dependent on test temperature. It was estimated that the 316 stainless steels would retain more than 1% true stains to necking at 164 o C after irradiation to 5 dpa. A calculation using reduction of area (RA) measurements and stress-strain data predicted positive strain hardening during plastic instability.

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The Accelerator Production of Tritium Materials Test Program

Cited by 8 publications

References 5 publications

Oxygen effects on irradiated tantalum alloys

Oxygen effects on irradiated tantalum alloys

The high temperature three point bend testing of proton irradiated 316L stainless steel and Mod 9Cr–1Mo

Temperature effects on the mechanical properties of candidate SNS target container materials after proton and neutron irradiation

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