Fuel Thermo-physical Characterization Project: Evaluation of Models to Calculate Thermal Diffusivity of Layered Composites

Burkes, Douglas¹  Casella, Amanda J.¹  Gardner, Levi D.¹  Casella, Andrew M.¹  Huber, Tanja K.²  Breitkreutz, Harald² 

[1]Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

[2]Technische Universit?��t M??nchen, Munich (Germany)

关键词: NUCLEAR FUELS;    THERMODYNAMIC PROPERTIES;    NUMERICAL ANALYSIS;    LAYERS uranium-molybdenum;    nuclear fuel;    thermal properties;    numerical analysis;    layers;   

DOI  :  10.2172/1177301
RP-ID  :  PNNL--24073
PID  :  OSTI ID: 1177301
Others  :  Other: NN9100000

美国|英语

来源: SciTech Connect

【 摘 要 】

The Office of Material Management and Minimization Fuel Thermo-physical Characterization Project at Pacific Northwest National Laboratory (PNNL) is tasked with using PNNL facilities and processes to receive irradiated low enriched uranium-molybdenum fuel plate samples and perform analyses in support of the Office of Material Management and Minimization Reactor Conversion Program. This work is in support of the Fuel Development Pillar that is managed by Idaho National Laboratory. A key portion of the scope associated with this project was to measure the thermal properties of fuel segments harvested from plates that were irradiated in the Advanced Test Reactor. Thermal diffusivity of samples prepared from the fuel segments was measured using laser flash analysis. Two models, one developed by PNNL and the other developed by the Technische Universit?��t M??nchen (TUM), were evaluated to extract the thermal diffusivity of the uranium-molybdenum alloy from measurements made on the irradiated, layered composites. The experimental data of the ???TC??? irradiated fuel segment was evaluated using both models considering a three-layer and five-layer system. Both models are in acceptable agreement with one another and indicate that the zirconium diffusion barrier has a minimal impact on the overall thermal diffusivity of the monolithic U-Mo fuel.