| | https://neup.inl.gov/SiteAssets/FY%202018%20Abstracts/CFA-18-14788_TechnicalAbstract_2018CFATechnicalAbstractCFA-18-14788.pdf | 18 | Aeroprobe | Nuclear Science User Facilities | Joint R&D with NSUF Access | $408,549.00 |
Researchers will perform irradiation and post-irradiation examination of materials produced by the MELD manufacturing process (FKA additive friction stir (AFS)) and analogous advanced manufacturing technologies. Compared with other additive manufacturing technique, MELD is much faster, generates a refined equiaxed structure, and does not require the post-manufacturing treatments needed for processes based on melting and solidification.
| |
| | https://neup.inl.gov/SiteAssets/FY%202018%20Abstracts/NSUF2-18-14783.pdf | 18 | Massachusetts Institute of Technology | Nuclear Science User Facilities | Joint R&D with NSUF Access | $481,433 | Researchers will study the neutron irradiation tolerance of nanodispersion strengthened composites produced by an innovative manufacturing method at low cost. The prolific internal interfaces between 1D/2D nanodispersions and the metal matrix provide radiation defect recombination venues to heal radiation damage. The success of this work will provide the novel concept of developing an innovative manufacturing method for advanced nuclear fuels and materials at low cost for long-term operation.
| |
| | https://neup.inl.gov/SiteAssets/FY%202018%20Abstracts/CFA-18-14749_TechnicalAbstract_2018CFATechnicalAbstract18-14749.pdf | 18 | The Ohio State University | Nuclear Science User Facilities | Joint R&D with NSUF Access | $500,000.00 |
The objective of this project is to perform a focused investigation of the irradiation behavior of piezoelectric aluminum nitride, a material considered as a highly attractive candidate for ultrasonic sensors in nuclear applications. In previous irradiation tests it has been identified as highly irradiation tolerant. The experiment will be designed to allow measurement of irradiation effects while isolating effects caused by transducer design.
| |
| | https://neup.inl.gov/SiteAssets/FY%202018%20Abstracts/CFA-18-14730_TechnicalAbstract_2018CFATechnicalAbstract14730.pdf | 18 | University of Notre Dame | Nuclear Science User Facilities | Joint R&D with NSUF Access | $500,000.00 |
This project aims to develop radiation-resistant nanostructured bulk thermoelectric materials and devices for in-pile power harvesting and sensing. The thermoelectric power harvesting technology has crosscutting significance to expand nuclear reactor sensing, instrumentation and offer major cost savings and enhanced safety for all reactor designs & fuel cycle concepts.
| |
| | https://neup.inl.gov/SiteAssets/FY%202018%20Abstracts/NSUF2-18-14772.pdf | 18 | Idaho National Laboratory | Nuclear Science User Facilities | NSUF Access Only | $0 | Researchers will investigate the swelling-related embrittlement behavior of AISI 316 stainless steels irradiated in fast reactor EBR-II at high neutron fluences.
| |
| | https://neup.inl.gov/SiteAssets/FY%202018%20Abstracts/NSUF2-18-14717.pdf | 18 | Oak Ridge National Laboratory | Nuclear Science User Facilities | NSUF Access Only | $0 | Researchers will demonstrate that ion irradiation can grow an existing damage microstructure to higher dose levels such that the doses provided by self-ion and neutron irradiation produces the same microstructure.
| |
| | https://neup.inl.gov/SiteAssets/FY%202018%20Abstracts/NSUF2-18-14787.pdf | 18 | Pacific Northwest National Laboratory | Nuclear Science User Facilities | NSUF Access Only | $0 | Researchers will perform higher-dose ion irradiation on neutron irradiated and unirradiated friction stir welded (FSW) MA956 alloy to understand microstructural evolution and radiation-hardening. The study will use ion irradiations and examination to understand and compare the effects of ion, neutron and neutron+ion irradiations.
| |
| | https://neup.inl.gov/SiteAssets/FY%202018%20Abstracts/NSUF2-18-14704.pdf | 18 | University of Florida | Nuclear Science User Facilities | NSUF Access Only | $0 | Researchers will increase the fundamental understanding of irradiation-induced metallic U-Pu-Zr fuel behavior and to obtain data needed for the development of irradiation models for metallic fuels in MARMOT. The project requests access to PIE facilities at NSUF partner facility to conduct examination of irradiated metallic fuels with the goal of providing foundational understanding of the radiation behavior in metallic fuels needed to inform the development of MARMOT models.
| |
