Yann Le Pape
- Name
- Yann Le Pape
- Institution
- Oak Ridge National Laboratory
| "Assessing the effects of gamma irradiation in concrete" Elena Tajuelo Rodriguez, William Hunnicutt, Paramita Mondal, Yann Le Pape, Transactions of the American Nuclear Society Vol. 118 2018 1649-1650 Link | ||
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"Direct Experimental Evidence for Differing Reactivity Alterations of Minerals following Irradiation: The Case of Calcite and Quartz"
Isabella Pignatelli, Yann Le Pape, Kevin Field,
Scientific Reports
Vol. 6
2016
20155
Concrete, used in the construction of nuclear power plants (NPPs), may be exposed to radiation emanating from the reactor core. Until recently, concrete has been assumed immune to radiation exposure. Direct evidence acquired on Ar+-ion irradiated calcite and quartz indicates, on the contrary, that, such minerals, which constitute aggregates in concrete, may be significantly altered by irradiation. More specifically, while quartz undergoes disordering of its atomic structure resulting in a near complete lack of periodicity, calcite only experiences random rotations, and distortions of its carbonate groups. As a result, irradiated quartz shows a reduction in density of around 15%, and an increase in chemical reactivity, described by its dissolution rate, similar to a glassy silica. Calcite however, shows little change in dissolution rate - although its density noted to reduce by ˜9%. These differences are correlated with the nature of bonds in these minerals, i.e., being dominantly ionic or covalent, and the rigidity of the mineral’s atomic network that is characterized by the number of topological constraints (nc) that are imposed on the atoms in the network. The outcomes have major implications on the durability of concrete structural elements formed with calcite or quartz bearing aggregates in nuclear power plants. |
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| "Elastic, Creep and Viscous response of gamma irradiated C-S-H" Elena Tajuelo Rodriguez, William Hunnicutt, Paramita Mondal, Yann Le Pape, Proceedings of the NICOM6 (Triennial international symposium of Nanotechnology in construction) Vol. [unknown] | ||
| "Examination of gamma irradiated C-S-H. Part I: Chemical-structural properties" William Hunnicutt, Elena Tajuelo Rodriguez, Paramita Mondal, Yann Le Pape, Journal of the American Ceramic Society Vol. 2019 Link | ||
| "Viscous behaviour of gamma irradiated C-S-H " Elena Tajuelo Rodriguez, William Hunnicutt, Yann Le Pape, Paramita Mondal, Proceedings of the 37th Cement and Concrete Science Conference Vol. 2017 63-66 Link |
| "Assessing the effects of gamma irradiation in concrete" Elena Tajuelo Rodriguez, William Hunnicutt, Paramita Mondal, Yann Le Pape, American Nuclear Society meeting June 17-21, (2018) | |
| "Elastic, Viscous and Creep response of Gamma irradiated C-S-H" Elena Tajuelo Rodriguez, William Hunnicutt, Paramita Mondal, Yann Le Pape, Triennial International Symposium of Nanotechnology in construction December 2-5, (2018) | |
| "Viscoelastic properties of gamma-irradiated calcium silicate hydrates" Elena Tajuelo Rodriguez, William Hunnicutt, Yann Le Pape, Paramita Mondal, 253rd National Meeting of the American Chemical Society April 2-6, (2017) | |
| "Viscous behaviour of gamma irradiated C-S-H" Elena Tajuelo Rodriguez, William Hunnicutt, Paramita Mondal, Yann Le Pape, 37th Cement and Concrete Science Conference September 11-12, (2017) |
Changes in mechanical and chemical-structural properties of gamma irradiated calcium silicate hydrates to an absorbed dose of 189 MGy with respect to pristine samples subjected to the same temperature history ProposalNew - FY 2021 RTE 1st Call, #4276
Changes on viscoelastic behavior, morphology and chemical structure of gamma irradiated calcium silicate hydrates to 0.96MGy with respect to non-irradiated samples - FY 2017 RTE 2nd Call, #960
Changes on viscoelastic behavior, morphology and chemical structure of gamma irradiated calcium silicate hydrates to 1.94 MGy with respect to non-irradiated samples - FY 2017 RTE 3rd Call, #1066
Changes on viscoelastic behavior, morphology and chemical structure of gamma irradiated calcium silicate hydrates with respect to non-irradiated samples - FY 2017 RTE 1st Call, #821
EBSD characterization of neutron irradiated mineral concrete aggregates - FY 2019 RTE 1st Call, #1693
Effect of neutron radiation on density and mechanical properties of concrete aggregates - FY 2021 RTE 1st Call, #4351
Effect of neutron radiation on density and mechanical properties of white cement paste - FY 2023 RTE 1st Call, #4573
In situ amorphization studies of forsterite, diopside and quartz under ion irradiation - FY 2017 RTE 3rd Call, #1090
About Us
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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