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Showing 1 to 13 of 13 for “"Accident Tolerant Fuel"”.
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Wettability of candidate Accident Tolerant Fuel (ATF) cladding materials in LWR conditions
Since the 2011 Fukushima accident, substantial research has been dedicated to developing accident tolerant fuel (ATF) cladding materials. These analyses have mostly concentrated on the capability of potential ATF materials to withstand runaway steam oxidation and preserve their mechanical strength …
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Estimation of coping time in pressurized water reactors for accident tolerant fuel claddings
The Fukushima Nuclear Power Plant (NPP) accident in Japan has motivated improving the safety of current light water reactors (LWRs). Accident tolerant fuels (ATF) are being developed to enhance the safety of LWRs by tolerating loss of active cooling in the core for a longer duration compared to …
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Impact of reactor environment on quenching heat transfer of accident tolerant fuel cladding
Development of accident tolerant fuels (ATF) for light water reactors (LWRs) came into focus for the nuclear engineering community after the accidents at Fukushima-Daiichi. The primary focus of the ATF program is to identify alternative fuel and cladding technologies that may provide enhanced …
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Analysis and optimization of a new accident tolerant fuel called fuel-in-fibers
The 2011 Fukushima Daiichi accident highlighted the weakness of the current nuclear fuel and motivated R&D of accident tolerant fuels. Accident tolerant fuels (ATF) are fuels that can tolerate loss of active cooling in the core of light water reactors (LWRs) for a considerably longer period of time …
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Fuel performance of multi-layered zirconium and silicon carbide based Accident Tolerant Fuel claddings
The Accident Tolerant Fuel (ATF) program is focused on extending the time for fuel failure during postulated severe accidents compared to the standard UO₂-Zr alloy fuel system. This thesis investigates the feasibility of four different cladding concepts, two of which are zirconium-alloy based and …
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Quantifying the fouling resistance of Accident-Tolerant Fuel (ATF) cladding coatings with force spectroscopy
… these CRUD forces were compared to other non-accident tolerant fuels, and there are cases in which non-ATF materials show more CRUD resistance (less adhesive force) than ATF-materials. This study's analysis could be applied to other materials to be used for reactor cladding. Once the material …
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Development of an experimental technique to investigate droplet cooling phenomena on accident tolerant fuel materials
… spray coolers in boiling water reactors. As new accident tolerant fuels are developed, understanding how they respond to droplet cooling is important to ensuring safe operations. Recent studies have indicated that surfaces engineered with micro- and nanostructures may affect the Leidenfrost point …
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Investigations on physical vapor deposition chromium coatings on Zircaloy-4 cladding using magnetron sputtering for accident tolerant fuel applications
Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2025-03-28 without embargo terms
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Material Corrosion by Nuclear Reactor Coolants
… and molten salt. Novel cladding materials for accident tolerant fuel (ATF) and additive manufacture (AM) Ni-based alloy were studied in water coolants. Similarly, the ATF material and Ni-based alloys were also examined under high-temperature steam to understand the corrosion behavior in beyond …
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Radiation Effects on Thermal Properties of Advanced Nuclear Materials
… fiber arrangements being evaluated for accident-tolerant fuel cladding applications. Complementary Thermal Conductivity Microscopy (TCM) measurements conducted at Idaho National Laboratory provided microscale resolution of constituent thermal properties, establishing a multi-scale …
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Investigation of Separate Effects of Surface Condition on Subcooled Flow Boiling Heat Transfer
… conditions. Importantly, the surface of a fuel rod cladding evolves during operation due to oxidation and crud deposition. Many studies have investigated the effects of surface properties (e.g., surface roughness, wettability, and porosity) on boiling heat transfer and CHF. Still, the …
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Application of advanced fuel concepts for use in innovative pressurized water reactors
… gaps that exist in the use of alternative fuel and cladding combinations in a pressurized water reactor (PWR) environment. In the switch from a UO2 with zirconium-based cladding to any other combination, there is a multitude of questions that need to be answered. This work examines three of …
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Response of chromium and chromium-aluminum coatings on zircaloy-2 to high temperature steam
High temperature steam exposure leads to rapid oxidation of Zr based cladding, which will potentially lead to cladding failure. Our approach is to apply CrAl or Cr coatings on Zircaloy by magnetron sputtering to improve the oxidation resistance of cladding materials. The goal of this research is to …