| | https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31388_TechnicalAbstract_2024CFATechnicalAbstract24-31388.pdf | 24 | Electric Power Institute, Inc. | Nuclear Science User Facilities | Access Only | $0 | The proposed research will utilize sets of utility owned irradiated RPV surveillance samples with variable fluence levels housed at the Westinghouse Churchill Site in Pittsburgh, PA. These sample sets, which have known fracture properties from prior destructive tests, will be utilized to determine if nonstandard nondestructive evaluation methods can be used to characterize fracture properties of reactor pressure vessel steels nondestructively. |
| | https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31397_TechnicalAbstract_2024CFATechnicalAbstractRPA-24-31397.pdf | 24 | Los Alamos National Laboratory | Nuclear Science User Facilities | Access Only | $0 | With the recent signing of Space Policy Directive-6, a US policy goal for micro nuclear reactor and space reactor systems has been designing these systems to utilize low-enriched uranium (LEU) ( |
| | https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31447_TechnicalAbstract_2024CFATechnicalAbstract24-31447.pdf | 24 | Pacific Northwest National Laboratory | Nuclear Science User Facilities | Access Only | $0 | Embrittlement of tempered martensitic (TM) steels is a key issue for their use in several advanced reactor concepts. PNNL has access to multiple TM steels irradiated in FFTF from 370-500°C with variations in C, Si, Mn, Ni, V, Cr, Mo, and N which all affect microstructure during irradiation. We will analyze mechanical properties and microstructure of selected TM steels to quantify the effects of elemental variations on radiation-induced precipitate formation and mechanical properties. |
| | https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31410_TechnicalAbstract.pdf | 24 | North Carolina State University | Nuclear Science User Facilities | Access with Research and Development Support | $1,100,000 | Project's objective is to gain a comprehensive understanding of neutron radiation damage at early stage and its impact on the mechanical deformation of high entropy alloys (HEAs) by employing a combination of mechanical testing, state-of-the-art microstructural characterization, and advanced modeling techniques. |
| | https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31320_TechnicalAbstract_2024CFATechnicalAbstract24-31320.pdf | 24 | Oregon State University | Nuclear Science User Facilities | Access with Research and Development Support | $1,000,000 | It has been shown that irradiation can enhance ordering in selected Ni-Cr based alloys via proton and neutron irradiation, however heavy ion irradiation to similar doses did not result in ordering. There is a trade-off between ballistic mixing and enhanced diffusion that may produce flux and cascade size dependent microstructures. This innovative project will be dedicated to uncovering the roles of irradiation-type (neutron and proton) in promoting long-range order in Ni-Cr based alloys. |
| | https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31412_TechnicalAbstract.pdf | 24 | University of Illinois at Urbana-Champaign | Nuclear Science User Facilities | Access with Research and Development Support | $1,100,000 | The objective of this project is to assess the mechanisms for initiation and development of irradiation-assisted stress corrosion cracking (IASCC) in austenitic stainless steel internal components, baffle-former bolts, harvested from a commercial pressurized water reactor (PWR). Core internal components of PWRs are subjected to high radiation doses, temperatures and corrosive environments. Advance microstructural characterization techniques are used to explain this degradation process. |
| | https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31374_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31374.pdf | 24 | University of Michigan | Nuclear Science User Facilities | Access with Research and Development Support | $1,000,000 | Optical sensors critically depend on the passage of light through transparent material. Most post-irradiation measurements reported in the literature have been performed with a significant delay after irradiation – from weeks to months. Significantly beyond the scope of prior studies, the team will carry out optical transmission measurements in bulk samples during material irradiation with gamma rays and neutrons and concurrent heating, and extend the in-situ characterization to shorter wavelengths. |
