scholarly journals Constituent Redistribution in U-Zr Metallic Fuel Using the Advanced Fuel Performance Code BISON

2016 ◽  
Author(s):  
Jack D. Galloway ◽  
Cetin Unal ◽  
Christopher Matthews
2015 ◽  
Vol 286 ◽  
pp. 1-17 ◽  
Author(s):  
J. Galloway ◽  
C. Unal ◽  
N. Carlson ◽  
D. Porter ◽  
S. Hayes

2021 ◽  
Vol 382 ◽  
pp. 111393
Author(s):  
Kyle M. Paaren ◽  
Micah Gale ◽  
Matthew J. Kerr ◽  
Pavel Medvedev ◽  
Douglas Porter

Energies ◽  
2021 ◽  
Vol 14 (2) ◽  
pp. 515
Author(s):  
Kyle M. Paaren ◽  
Nancy Lybeck ◽  
Kun Mo ◽  
Pavel Medvedev ◽  
Douglas Porter

BISON finite element method fuel performance simulations were conducted using an existing automated process that couples the Fuels Irradiation & Physics Database (FIPD) and the Integral Fast Reactor Materials Information System database by writing input files and comparing the BISON output to post-irradiation fuel pin profilometry measurements contained within the databases. The importance of this work is to demonstrate the ability to benchmark fuel performance metallic fuel models within BISON using Experimental Breeder Reactor-II fuel pin data for a number of similar pins, while building off previous modeling efforts. Changes to the generic BISON input file include implementing pin specific axial power and flux profiles, pin specific fluences, frictional contact, and irradiation-induced volumetric swelling models for cladding. A statistical analysis of irradiation-induced volumetric swelling models for HT9, D9, and SS316 was performed for experiments X421/X421A, X441/X441A, and X486. Between these three experiments, there were 174 post-irradiation examination (PIE) profilometries used for validating the swelling models presented using a standard error of the estimate (SEE) method. Implementation of the volumetric swelling models for D9 and SS316 claddings was found to have a significant impact on the BISON profilometry simulated, where HT9 clad pins had an insignificant change due to low fluence values. BISON profilometry simulated for HT9, D9, and SS316 fuel pins agreed with PIE profilometry measurements, with assembly SEE values being 4.4 × 10−3 for X421A, 2.0 × 10−3 for X441A, and 2.8 × 10−3 for X486. D9 clad pins in X421/X421A had the highest SEE values, which is due to the BISON simulated profilometry being shifted axially. While this work accomplished its purpose to demonstrate the modeling of multiple fuel pins from the databases to help validate models, the results suggest that the continued development of metallic fuel models is necessary for qualifying new metallic fuel systems to better capture some physical performance phenomena, such as the hot pressing of U-Pu-Zr and the fuel cladding chemical interaction.


2021 ◽  
Author(s):  
Jake Hirschhorn ◽  
Ryan Sweet ◽  
Jeffrey Powers

1998 ◽  
Vol 123 (2) ◽  
pp. 130-141 ◽  
Author(s):  
Woan Hwang ◽  
Cheol Nam ◽  
Thak Sang Byun ◽  
Young Cheol Kim

2020 ◽  
Author(s):  
Ian Greenquist ◽  
Kaylee Cunningham ◽  
Jianwei Hu ◽  
Jeffrey Powers

Author(s):  
Hangbok Choi ◽  
Joshua Stone

Advanced reactor concepts such as Generation-IV (Gen-IV) have been studied to fulfill the ambitious long term goals of developing a safe, sustainable, reliable, proliferation-resistant and economic nuclear energy system. The gas-cooled fast reactor (GFR) is a Gen-IV candidate for which a carbide fuel (UC, (U,Pu)C, ThC) has desirable properties in a fuel system using ceramic (SiC) cladding. This study reviews advanced fuel concepts and associated fabrication methods for a GFR, followed by available carbide fuel property data, update of fuel performance code, and assessment of the fuel performance analysis model based on irradiation test results in the Fast Flux Test Facility. The purpose of this study is to develop a fuel performance code for the design and analysis of carbide fuel and to verify the implementation of fuel property models using earlier fuel irradiation tests jointly conducted by US and Switzerland. The comparison of carbide fuel simulation results to the experimental data shows differences in the prediction of fuel temperature and swelling. Considering the limitation and uncertainty of the existing material property data, the results obtained from the updated fuel performance code indicate that more work is required to adjust and update some of the carbide fuel material property models. In the future, the coolant model will also be updated for the flexibility of code application to various advanced fuel analyses. In the long term, the code will be used for the evaluation of advanced carbide fuel with ceramic cladding and the simulation of carbide fuel irradiation tests.


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