Search

Your search keyword '"Terrani, Kurt A."' showing total 422 results
Start Over Author "Terrani, Kurt A."
422 results on '"Terrani, Kurt A."'

8. PWR core design with Metal Matrix Micro-encapsulated (M3) fuel

Author

Fratoni, Massimiliano and Terrani, Kurt A

Subjects
Energy
Abstract

Metal Matrix Micro-encapsulated (M3) fuel consists of TRISO coated fuel particles directly dispersed in a matrix of zirconium metal to form a solid rod. In this integral fuel concept the cladding tube and the failure mechanisms associated with it have been eliminated; therefore, M3 fuel, compared to existing fuel designs, is expected to provide greatly improved operational performance. The main challenge to the deployment of M3 fuels is the low heavy metal load. This needs to be compensated with high density fuel (uranium nitride), larger rods and mainly higher enrichment. This study found that M3 fuel requires about 15.5% enriched UN TRISO particles to match the cycle length of standard fuel when loaded in a PWR. In order to achieve comparable reactivity feedbacks, in particular moderator temperature, the pitch to rod diameter ratio should be reduced to 1.20 compared to the typical 1.326. As M3 fuel provides a better path for heat transfer from the fuel, such smaller pitch is expected to be feasible, but further evaluations especially to examine thermal-hydraulic aspects are required. Analyses of possible load patterns for burnable poisons showed that M3 fuel maintains similar cycle length to that of standard fuel and pin power peaks are also comparable. Nevertheless, further optimization will be required to limit assembly power peaks.

Published
2017

29. The Mechanical Response Evaluation of Advanced Claddings During Proposed Reactivity Initiated Accident Conditions

Author

Nedim Cinbiz, M., Brown, Nicholas, Terrani, Kurt A., Lowden, Rick R., Erdman, Donald, III, Liu, Xingbo, editor, Liu, Zhengdong, editor, Brinkman, Kyle, editor, Das, Subodh, editor, Dryepondt, Sebastien, editor, Fergus, Jeffrey W., editor, Guo, Zhancheng, editor, Han, Minfang, editor, Hawk, Jeffrey A., editor, Horita, Teruhisa, editor, Hosemann, Peter, editor, Li, Jian, editor, Olivetti, Elsa, editor, Pandey, Amit, editor, Rebak, Raul B., editor, Roy, Indranil, editor, Shang, Chengjia, editor, and Zhang, Ji, editor

Published
2017
Full Text
View/download PDF

37. Mechanical and Thermophysical Properties of 3D-Printed SiC before and after Neutron Irradiation – FY21

Author

Byun, T., primary, Lach, Tim, additional, Parish, Chad, additional, Wang, Hsin, additional, Trofimov, Artem, additional, Collins, David, additional, Le Coq, Annabelle, additional, Linton, Kory, additional, Richardson, M., additional, Jolly, Brian, additional, Trammell, Michael, additional, Schumacher, Austin, additional, Vasudevamurthy, Gokul, additional, Koyanagi, Takaaki, additional, and Terrani, Kurt, additional

Published
2021
Full Text
View/download PDF

49. ARTIFICIAL INTELLIGENCE DESIGN OF NUCLEAR SYSTEMS EMPOWERED BY ADVANCED MANUFACTURING

Author

Sobes Vladimir, Hiscox Briana, Popov Emilian, Delchini Marco, Archibald Richard, Hauck Cory, Laiu Paul, Betzler Ben, and Terrani Kurt

Subjects
nuclear systems design, optimization, arbitrary geometry, artificial intelligence, Physics, QC1-999
Abstract

Implicit in any engineering design is an underlying optimization problem, although the exact objective function to be optimized is rarely stated explicitly. Nuclear systems optimization is as old as the discipline of nuclear engineering. Advanced manufacturing in the nuclear industry has opened the door for the re-examination of optimization in a way in which it was not possible before, namely, determining the optimal geometry for a given objective function. A trivial example is the sphere as the shape that minimizes the volume (or mass) of bare fissile material in a critical configuration. However, the problem becomes less trivial under even the simplest of multiphysics considerations. In this work, we develop the solution methodology for finding the minimum volume geometric configurations under the multiphysics constraints of 1,500 pcm excess reactivity and maximum fuel temperature of 618°C under forced-flow cooling conditions. Constraining the solution geometry only to right cylinders, surprisingly yields two disjoint solution regions. Flat, wide (disk-like) cylinders and tall, narrow (rod-like) cylinders both satisfy the constraints and yield very similar minimal volumes. However, the ultimate pursuit of this work is truly arbitrary geometry.

Published
2021
Full Text
View/download PDF

Catalog

Books, media, physical & digital resources
See catalog results