"Application of NSUF Capabilities Towards Understanding the Emulation of High Dose Neutron Irradiations with Ion Beams" Kevin Field, Stephen Taller, Christopher Ulmer, Zhijie Jiao, Tarik Saleh, Arthur Motta, Gary Was, Transactions of the American Nuclear Society Vol. 116 2017 Link | ||
"Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ˜295 °C to ˜6.5 dpa"
Stuart Maloy, G. Robert Odette, Tarik Saleh, Takuya Yamamoto, Osman Anderoglu, T. J. Romero, Shuangchen Li, James Cole, Randall Fielding,
Journal of Nuclear Materials
Vol. 468
2016
232-239
Link
Tensile test results at 25 and 300 °C on five 9-12Cr tempered martensitic steels and one 14Cr oxide dispersion strengthened alloy, that were side-by side irradiated to 6.5 dpa at 295 °C in the Advanced Test Reactor (ATR), are reported. The engineering stress–strain curves are analyzed to provide true stress–strain constitutive σ(ε) laws for all of these alloys. In the irradiated condition, the σ(ε) fall into categories of: strain softening, nearly perfectly plastic and strain hardening. Increases in yield stress (Δσy) and reductions in uniform strain ductility (eu) are observed, where the latter can be understood in terms of the alloy's σ(ε) behavior. Increases in the average σ(ε) in the range of 0–10% strain are smaller than the corresponding Δσy, and vary more from alloy to alloy. The data are also analyzed to establish relations between Δσy and coupled changes in the ultimate stresses as well as the effects of both test temperature and the unirradiated yield stress (σyu). The latter shows that higher σyu correlates with lower Δσy. In five out of six cases the effects of irradiation are generally consistent with previous observations on these alloys. However, the particular heat of the 12Cr HT-9 tempered martensitic steel in this study has a much higher eu than observed for earlier heats. The reasons for this improved behavior are not understood and may be microstructural in origin. However, it is noted that the new heat of HT-9, which was procured under modern quality assurance standards, has lower interstitial nitrogen than previous heats. Notably lower interstitial solute contents correlate with improved ductility and homogenous deformation in broadly similar steels. |
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"Direct comparison of nanoindentation and tensile test results on reactor-irradiated materials" David Krumwiede, Takuya Yamamoto, Tarik Saleh, Stuart Maloy, G. Robert Odette, Peter Hosemann, Journal of Nuclear Materials Vol. 504 2018 135-143 Link | ||
"Neutron irradiation induced defects and clustering in NF616 and T91" Weicheng Zhong, Tarik Saleh, Lizhen Tan, Journal of Nuclear Materials Vol. 552 2021 Link |
"Application of NSUF Capabilities Towards Understanding the Emulation of High Dose Neutron Irradiations with Ion Beams" Kevin Field, Zhijie Jiao, Tarik Saleh, Stephen Taller, Gary Was, 2017 ANS Annual Meeting [unknown] | |
"Development and Testing Advanced Ferritic Steels for Fast Reactor Applications" Osman Anderoglu, Stuart Maloy, G. Robert Odette, Tarik Saleh, TMS 2014 February 16-20, (2014) | |
"Post Irradiation Examination of Fast Neutron Irradiated 14YWT Tubes at Nuclear Science User Facilities" Eda Aydogan, Peter Hosemann, David Krumwiede, Stuart Maloy, Tarik Saleh, 2017 ANS Annual Meeting [unknown] |
U.S. Department of Energy Announces FY17 CINR FOA Awards - DOE selected 14 NSUF projects DOE selected five university, four national laboratory, and five industry-led projects that will take advantage of NSUF capabilities to investigate important nuclear fuel and material applications. Wednesday, September 20, 2017 - Calls and Awards |
Users Organization Meeting Presentations Now Available - Wednesday, March 25, 2020 - Newsletter, Users Group |
"Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at approximate to 295 degrees C to approximate to 6.5 dpa" T.A. Saleh, O. Anderoglu, T.J. Romero, G.R. Odette, T. Yamamoto, S. Li, J.I. Cole, R. Fielding, S.A. Maloy, [2016] JOURNAL OF NUCLEAR MATERIALS · DOI: 10.1016/j.jnucmat.2015.07.039 | |
"Proton irradiation damage of an annealed Alloy 718 beam window" O. Anderoglu, T.A. Saleh, T.J. Romero, C.T. Kelsey, E.R. Olivas, B.H. Sencer, P.O. Dickerson, M.A. Connors, K.D. John, S.A. Maloy, H.T. Bach, [2015] JOURNAL OF NUCLEAR MATERIALS · DOI: 10.1016/j.jnucmat.2014.12.096 | |
"Deformation processes and casting behavior of unalloyed Pu" [2014] Plutonium Futures: The Science 2014 · EID: 2-s2.0-84944874486 | |
"Elastic moduli and nonlinear resonance ultrasound spectroscopy studies of alpha plutonium rods" [2014] Plutonium Futures: The Science 2014 · EID: 2-s2.0-84944905134 | |
"Probing material nonlinearity at various depths by time reversal mirrors"
T. J. Ulrich, P. Y. Le Bas, M. Griffa, P. Schuetz, M. C. Remillieux, T. A. Saleh, C. Payan,
[2014]
Applied Physics Letters
· DOI: 10.1063/1.4871094
· EID: 2-s2.0-84898973701
In this Letter, the time reversal mirror is used to focus elastic energy at a prescribed location and to analyze the amplitude dependence of the focus signal, thus providing the nonlinearity of the medium. By varying the frequency content of the focused waveforms, the technique can be used to probe the surface, by penetrating to a depth defined by the wavelength of the focused waves. The validity of this concept is shown in the presence of gradual and distributed damage in concrete by comparing actual results with a reference nonlinear measurement and X ray tomography images. |
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"Quantitative linear and nonlinear resonance inspection techniques and analysis for material characterization: Application to concrete thermal damage"
T. J. Ulrich, P. Y. Le Bas, T. Saleh, M. Guimaraes, C. Payan,
[2014]
Journal of the Acoustical Society of America
· DOI: 10.1121/1.4887451
· EID: 2-s2.0-84905678746
Developed in the late 1980s, Nonlinear Resonant Ultrasound Spectroscopy (NRUS) has been widely employed in the field of material characterization. Most of the studies assume the measured amplitude to be proportional to the strain amplitude which drives nonlinear phenomena. In 1D resonant bar experiments, the configuration for which NRUS was initially developed, this assumption holds. However, it is not true for samples of general shape which exhibit several resonance mode shapes. This paper proposes a methodology based on linear resonant ultrasound spectroscopy, numerical simulations and nonlinear resonant ultrasound spectroscopy to provide quantitative values of nonlinear elastic moduli taking into account the 3D nature of the samples. In the context of license renewal in the field of nuclear energy, this study aims at providing some quantitative information related to the degree of micro-cracking of concrete and cement based materials in the presence of thermal damage. The resonance based method is validated as regard with concrete microstructure evolution during thermal exposure. |
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"Quantitative linear and nonlinear resonance inspection techniques and analysis for material characterization Application to concrete thermal damage"
T. J. Ulrich, P. Y. Le Bas, T. Saleh, M. Guimaraes, C. Payan,
[2014]
Journal of the Acoustical Society of America
· DOI: 10.1121/1.4887451
Developed in the late 1980s, Nonlinear Resonant Ultrasound Spectroscopy (NRUS) has been widely employed in the field of material characterization. Most of the studies assume the measured amplitude to be proportional to the strain amplitude which drives nonlinear phenomena. In 1D resonant bar experiments, the configuration for which NRUS was initially developed, this assumption holds. However, it is not true for samples of general shape which exhibit several resonance mode shapes. This paper proposes a methodology based on linear resonant ultrasound spectroscopy, numerical simulations and nonlinear resonant ultrasound spectroscopy to provide quantitative values of nonlinear elastic moduli taking into account the 3D nature of the samples. In the context of license renewal in the field of nuclear energy, this study aims at providing some quantitative information related to the degree of micro-cracking of concrete and cement based materials in the presence of thermal damage. The resonance based method is validated as regard with concrete microstructure evolution during thermal exposure. |
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"Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF" Mychailo B. Toloczko, Tarik A. Saleh, Stuart A. Maloy, Thak Sang Byun, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2012.07.019 | |
"In situ neutron diffraction and Elastic-Plastic Self-Consistent polycrystal modeling of HT-9" D.W. Brown, M.A.M. Bourke, T.A. Saleh, S.A. Maloy, B. Clausen, [2012] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2011.05.011 | |
"Probing materials damage at various depths by use of Time Reversal Elastic Nonlinearity Diagnostic: Application to concrete" T. J. Ulrich, Pierre-Yves Le Bas, Tarik Saleh, M. Guimaraes, Cedric Payan, [2012] Proceedings of Meetings on Acoustics · DOI: 10.1121/1.4764477 · EID: 2-s2.0-84878999948 | |
"Mechanical behavior of alpha, beta, and gamma plutonium" T.A. Saleh, F.J. Freibert, M.E. Bange, A.M. Farrow, [2011] Procedia Engineering · DOI: 10.1016/j.proeng.2011.04.535 | |
"Phase-transformation and subgrain-deformation characteristics in a cobalt-based superalloy" B. Reetz, P.K. Liaw, W. Reimers, H. Choo, D.W. Brown, T.A. Saleh, D.L. Klarstrom, M.L. Benson, [2011] Materials Science and Engineering A · DOI: 10.1016/j.msea.2010.10.061 | |
"Temperature dependence of elastic moduli of polycrystalline beta plutonium" V. R. Fanelli, J. B. Betts, F. J. Freibert, C. H. Mielke, J. N. Mitchell, M. Ramos, T. A. Saleh, A. Migliori, Yoko Suzuki, [2011] PHYSICAL REVIEW B · DOI: 10.1103/physrevb.84.064105 | |
"Microstructure and thermophysical characterization of mixed oxide fuels"
Tarik A. Saleh, Fred G. Hampel, Daniel S. Schwartz, Jeremy N. Mitchell, Charles C. Davis, Angelique D. Neuman, Stephen P. Willson, John T. Dunwoody, Franz J. Freibert,
[2010]
Materials Research Society Symposium Proceedings
· DOI: 10.1557/proc-1215-v10-06
Pre-irradiated thermodynamic and microstructural properties of nuclear fuels form the necessary set of data against which to gauge fuel performance and irradiation damage evolution. This paper summarizes recent efforts in mixed-oxide and minor actinide-bearing mixed-oxide ceramic fuels fabrication and characterization at Los Alamos National Laboratory. Ceramic fuels (U1-x-y-zPuxAmyNpz)O2 fabricated in the compositional ranges of 0.19≤x≤0.3 Pu, 0≤y≤0.05 Am, and 0≤z≤0.03 Np exhibited a uniform crystalline face-centered cubic phase with an average grain size of 14μm; however, electron microprobe analysis revealed segregation of NpO2 in minor actinide-bearing fuels. Immersion density and porosity analysis demonstrated an average density of 92.4% theoretical for mixed-oxide fuels and an average density of 89.5% theoretical density for minor actinide-bearing mixed-oxide fuels. Examined fuels exhibited mean thermal expansion value of 12.56×10−6/°C-1 for temperature range (100°C<T<1500°C) and ambient temperature Young's modulus and Poisson's ratio of 169 GPa and of 0.327, respectively. Internal dissipation as determined from mechanical resonances of these ceramic fuels has shown promise as a tool to gauge microstructural integrity and to interrogate fundamental properties. |
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"Thermophysical properties of coexistent phases of plutonium" J N Mitchell, T A Saleh, D S Schwartz, F J Freibert, [2010] IOP Conference Series Materials Science and Engineering · DOI: 10.1088/1757-899x/9/1/012096 | |
"In situ neutron-diffraction study of tensile deformation of a bulk nanocrystalline alloy" L. Li, Bin Yang, H. Choo, P.K. Liaw, T.A. Saleh, B. Clausen, D.W. Brown, G.J. Fan, [2009] MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING · DOI: 10.1016/j.msea.2008.11.054 | |
"Strain-dependent deformation behavior in nanocrystalline metals" Hahn Choo, Yang Ren, Tarik A. Saleh, Ulrich Lienert, Peter K. Liaw, Fereshteh Ebrahimi, Hongqi Li, [2008] PHYSICAL REVIEW LETTERS · DOI: 10.1103/physrevlett.101.015502 | |
"In-situ electrochemical investigations of a nickel-based alloy subjected to fatigue" G. Wang, R.A. Buchanan, P.K. Liaw, T.A. Saleh, D.L. Klarstrom, S.N. Meck, R.V. Steward, [2007] METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE · DOI: 10.1007/s11661-007-9231-5 | |
"Deformation-induced phase development in a cobalt-based superalloy during monotonic and cyclic deformation" P.K. Liaw, T.A. Saleh, H. Choo, D.W. Brown, M.R. Daymond, E.-W. Huang, X.-L. Wang, A.D. Stoica, R.A. Buchanan, D.L. Klarstrom, M.L. Benson, [2006] PHYSICA B-CONDENSED MATTER · DOI: 10.1016/j.physb.2006.05.262 | |
"Intergranular strain and phase transformation in a cobalt-based superalloy"
A.D. Stoica, Peter K. Liaw, Hahn Choo, T.A. Saleh, X.L. Wang, Donald W. Brown, Dwaine L. Klarstrom, Michael L. Benson,
[2006]
Materials Science Forum
· DOI: 10.4028/www.scientific.net/msf.524-525.893
ULTIMET® alloy, a cobalt-based superalloy with good corrosion and wear resistant properties, exhibits a deformation-induced phase transformation from the face-centered-cubic (FCC) phase to the hexagonal-close-packed (HCP) phase. The HCP phase formation during monotonic tensile loading was investigated using in-situ neutron diffraction. The HCP phase is first observed at a stress level of 810 MPa, which is well beyond macroscopic yielding. Strain analysis is performed on the FCC phase diffraction data in order to relate the lattice-strain development with the evolution of the new HCP phase. A method of calculating the effective macroscopic stress associated with the measured lattice strains is presented here. The effective stress can then be compared to the applied macroscopic stress in order to draw conclusions about the load-partitioning behavior of the material as a new phase develops. |
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Source: ORCID/CrossRef using DOI |
Elemental effects on radiation damage in tempered martensitic steels neutron irradiated to high doses at fast reactor relevant temperatures - FY 2024 CINR, #24-31447
In situ TEM studies on thermodynamic stability and microstructural evolution of zirconium hydrides in irradiation and thermal environments - FY 2022 RTE 1st Call, #22-4434
In-Situ SEM Irradiation Enhanced Creep Studies of 14 YWT - FY 2019 RTE 1st Call, #19-1648
A study of the tensile response of HT-9 alloys following ATR irradiation to doses between 0.01 and 10 dpa at 300, 450 and 550C - FY 2019 RTE 1st Call, #19-1670
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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