Evaluating Fuel Behavior During Irradiation by Fission-gas Release
Title | Evaluating Fuel Behavior During Irradiation by Fission-gas Release PDF eBook |
Author | |
Publisher | |
Pages | 0 |
Release | 1970 |
Genre | Fission products |
ISBN |
Uncertainty and Sensitivity Analysis of Fission Gas Behavior in Engineering-scale Fuel Modeling
Title | Uncertainty and Sensitivity Analysis of Fission Gas Behavior in Engineering-scale Fuel Modeling PDF eBook |
Author | |
Publisher | |
Pages | 11 |
Release | 2014 |
Genre | |
ISBN |
The role of uncertainties in fission gas behavior calculations as part of engineering-scale nuclear fuel modeling is investigated using the BISON fuel performance code and a recently implemented physics-based model for the coupled fission gas release and swelling. Through the integration of BISON with the DAKOTA software, a sensitivity analysis of the results to selected model parameters is carried out based on UO2 single-pellet simulations covering different power regimes. The parameters are varied within ranges representative of the relative uncertainties and consistent with the information from the open literature. The study leads to an initial quantitative assessment of the uncertainty in fission gas behavior modeling with the parameter characterization presently available. Also, the relative importance of the single parameters is evaluated. Moreover, a sensitivity analysis is carried out based on simulations of a fuel rod irradiation experiment, pointing out a significant impact of the considered uncertainties on the calculated fission gas release and cladding diametral strain. The results of the study indicate that the commonly accepted deviation between calculated and measured fission gas release by a factor of 2 approximately corresponds to the inherent modeling uncertainty at high fission gas release. Nevertheless, higher deviations may be expected for values around 10% and lower. Implications are discussed in terms of directions of research for the improved modeling of fission gas behavior for engineering purposes.
A Method for the Study and Correlation of Fission-gas-release Behavior of Fuel Materials During Irradiation
Title | A Method for the Study and Correlation of Fission-gas-release Behavior of Fuel Materials During Irradiation PDF eBook |
Author | Gilbert E. Raines |
Publisher | |
Pages | 100 |
Release | 1961 |
Genre | Fission gases |
ISBN |
Assessment of FRAPCON-1 BE/EM Calculated Fission Gas Release in RISO Fuel Rods
Title | Assessment of FRAPCON-1 BE/EM Calculated Fission Gas Release in RISO Fuel Rods PDF eBook |
Author | Rosanna Chambers |
Publisher | |
Pages | 28 |
Release | 1980 |
Genre | Nuclear fuel rods |
ISBN |
Post-irradiation evaluation of fuel elements irradiated in superheated steam : Part 2 fission gas release
Title | Post-irradiation evaluation of fuel elements irradiated in superheated steam : Part 2 fission gas release PDF eBook |
Author | D. M. Evans |
Publisher | |
Pages | 0 |
Release | 1964 |
Genre | |
ISBN |
Analysis of Fission-gas Behavior with the Stars Code
Title | Analysis of Fission-gas Behavior with the Stars Code PDF eBook |
Author | Eugene E. Gruber |
Publisher | |
Pages | 36 |
Release | 1988 |
Genre | Fission gases |
ISBN |
Nuclear Fuel Elements
Title | Nuclear Fuel Elements PDF eBook |
Author | Brian R. T. Frost |
Publisher | Elsevier |
Pages | 284 |
Release | 2013-10-22 |
Genre | Technology & Engineering |
ISBN | 1483155250 |
Nuclear Fuel Elements: Design, Fabrication and Performance is concerned with the design, fabrication, and performance of nuclear fuel elements, with emphasis on fast reactor fuel elements. Topics range from fuel types and the irradiation behavior of fuels to cladding and duct materials, fuel element design and modeling, fuel element performance testing and qualification, and the performance of water reactor fuels. Fast reactor fuel elements, research and test reactor fuel elements, and unconventional fuel elements are also covered. This volume consists of 12 chapters and begins with an overview of nuclear reactors and fuel elements, as well as fuel element design and development based on the reactor operator's approach, materials scientist's approach, and interdisciplinary approach. The reader is then introduced to different types of nuclear fuels and their irradiation behavior, considerations for using cladding and duct materials in fuel element design and development, and fuel element design and modeling. The chapters that follow focus on the testing of fuel element performance, experimental techniques and equipment for testing fuel element designs, and the performance of fuels for water reactors. Fuel elements for gas-cooled reactors, fast reactors, and research and test reactors are also described. The book concludes with an assessment of unconventional fuel elements. This book will be useful to fuel element technologists as well as materials scientists and engineers.