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Milos Atz
Milos Atz
Ultra Safe Nuclear Corporation
在 usnc.com 的电子邮件经过验证
标题
引用次数
引用次数
年份
DASSH software for ducted assembly thermal hydraulics calculations–overview and benchmark
M Atz, MA Smith, F Heidet
Transactions of the American Nuclear Society 123 (2020), 2020
142020
Ducted Assembly Steady-State Heat Transfer Software (DASSH): Theory Manual
M Atz, MA Smith, F Heidet
Argonne National Lab.(ANL), Argonne, IL (United States), 2021
72021
Assessment of the potential for criticality in the far field of a used nuclear fuel repository
M Atz, A Salazar, F Hirano, M Fratoni, J Ahn
Annals of Nuclear Energy 124, 28-38, 2019
52019
Methodologies for the Evaluation of Nuclear Waste Management Strategies and Applications to Advanced Fuel Cycles
MI Atz
University of California, Berkeley, 2019
52019
Attractiveness of Fissile material in nuclear wastes from different fuel cycles
MI Atz, M Fratoni
Nuclear Technology 210 (5), 795-813, 2024
42024
A Framework to Assess Advanced Reactor Spent Fuel Management Facility Deployment
MI Atz, RA Joseph, EA Hoffman
Nuclear Technology, 1-21, 2024
42024
Nuclear waste Educator's workshop: What and how do we teach about nuclear waste?
HM Wainwright, BA Powell, ME Hoover, A Ayoub, M Atz, C Benson, ...
Journal of Environmental Radioactivity 270, 107288, 2023
42023
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel Cycles
MI Atz, M Fratoni
Nuclear Technology 209 (8), 1109-1128, 2023
42023
Estimation of waste package inventories and characteristics from different advanced fuel cycles
MI Atz, M Fratoni
Nuclear Technology 209 (5), 677-695, 2023
42023
Ducted Assembly Steady State Heat Transfer Software (DASSH)-User Guide
M Atz, MA Smith, F Heidet
ANL/NSE-21/34, Argonne National Laboratory, 2021
42021
VTR Core Design Analyses Supporting Flexible Operations
A Kasam-Griffith, M Atz, T Fei, Z Zhong, M Jarrett, F Heidet
Nuclear Science and Engineering 196 (sup1), 38-49, 2022
32022
PyARC-A user-friendly open-source reactor physics framework for fast reactor design and analysis
NE Stauff, A Abdelhameed, M Atz, P Shriwise, YS Jung, R Lefebvre
Proceedings of the international conference on physics of reactors-PHYSOR 2022, 2022
32022
Performance of HALEU and HEU-fueled nuclear thermal propulsion reactors
AG Nelson, AA Kasam-Griffith, MI Atz, F Heidet
Argonne National Lab.(ANL), Argonne, IL (United States), 2021
32021
Status of the NEAMS and ARC fast reactor tools integration to the NEAMS Workbench
N Stauff, M Atz, A Abdelhameed, K Kiesling, S Kumar, Y Jung, P Shriwise
Argonne National Laboratory (ANL), Argonne, IL (United States), 2022
22022
DUCTED ASSEMBLY STEADY STATE HEAT TRANSFER SOFTWARE
MI ATZ, MA SMITH, F HEIDET
Argonne National Lab.(ANL), Argonne, IL (United States), 2020
22020
Impact of partitioning and transmutation on the back end of the fuel cycle
M Atz, M Fratoni
Proc. 15th Int. Exchange Mtg. on Actinide and Fission Product Partitioning …, 2018
22018
Cross-disciplinary Reactor-to-Repository Framework for Evaluating Spent Nuclear Fuel from Advanced Reactors
HM Wainwright, C Christiaen, M Atz, JS Tchakerian, J Yu, GK Ridley, ...
arXiv preprint arXiv:2405.12805, 2024
12024
Impact of Interim Storage on Repository Design Options
M Atz, M Fratoni
International High-Level Radioactive Waste Management (IHLRWM 2019), 172-177, 2019
12019
The Criticality Safety Studies of Joonhong Ahn
A Salazar, M Atz, X Liu, M Fratoni
Transactions of the American Nuclear Society 116, 110-113, 2017
12017
A multidisciplinary framework from reactors to repositories for evaluating spent nuclear fuel from advanced reactors
HM Wainwright, C Christiaen, M Atz, JS Tchakerian, J Yu, GK Ridley, ...
Scientific Reports 14 (1), 26904, 2024
2024
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