Development of a Thermal Creep Model for Aluminum Alloy 6061 Cladding in U-10Mo Monolithic Fuel Plates
Plate-type fuel elements consisting of a high-density, low-enriched uranium (LEU) U–10Mo-based fuel foil encapsulated in an aluminum alloy (AA) cladding are fabricated using the hot isostatic pressing (HIP) technique. During the HIP process, the fuel plate system is heated to 560 degree celsius, then cooled to room temperature. This heat cycle significantly affects the mechanical […]
Evaluation of U10Mo Fuel Plate Performance modeling over Hot Isostatic Press and Hydraulic Bending for MURR-DDE Plates
The United States-High Performance Research Reactor (USHPRR) program’s objective is to reduce the amount of highly enriched uranium (HEU) currently implemented in research reactors. The conversion of these research reactors requires the design of a monolithic U10Mo plate fuel, with the geometry of the fuel plate being dependent on each research reactor. The process of […]
Mechanical Properties of Irradiated U-10?wt. %Mo Alloy Degraded by Porosity Development
A plate-type nuclear fuel consisting of a solid monolithic foil of U-10wt%Mo is under development for use in the United States’ high performance research reactors. In support of developing this fuel, the fuel has been fabricated for the first time by a commercial fuel vendor and subsequently irradiated in a test reactor. This provides an […]
Unraveling the Mechanics: Computational Modeling of Residual Stresses in U10Mo Fuel with Aluminum Cladding
LEU (Low Enriched Uranium) plate-type fuel elements consist of a high-density, low-enrichment U–Mo alloy-based fuel foil encapsulated in an aluminum cladding and is fabricated through the Hot Isostatic Pressing (HIP) technique. Understanding the mechanism of possible failure modes of nuclear fuel is critical to mitigate potential consequences. One of the major contributing factors in various […]
Fluid structural interaction simulation of the MP-1 plate performance irradiated in the advanced test reactor
Due to the high neutron fluxes they generate and increased heat transfer performance, plate type fuels are used in the U.S. high-performance research reactors. During irradiation, a significant amount of fission energy (i.e., ~200 MeV per atom) is released by the U-235 chain reaction that is carried away by the coolant. Through thermal hydraulic analysis, […]
Overview of Base Model in Parametric Studies Specific to Performance of U-Mo Plates
This paper provides an overview of the base model specifically developed to perform parametric sensitivity studies on the U-10Mo monolithic fuel system. U-Mo monolithic fuels are being considered for the conversion of test reactors into high-performance research reactors that operate using proliferation-resistant, low-enriched uranium (LEU) fuels. These plate-type fuels contain a high-density, low-enrichment fuel sandwiched […]
Review of Graphite Properties Relevant to Micro-Reactor Design
Microreactors are advanced reactors that are designed to be small, scalable, and portable with up to 20 MW power. These reactors could operate independently, or as part of a microgrid, without need of a frequent refueling. Micro-reactors are designed to be deployable to provide electric power in remote locations, therefore providing greater flexibility. Several micro-reactors […]