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Andrei Rykhlevskii
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Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor
A Rykhlevskii, JW Bae, KD Huff
Annals of Nuclear Energy 128, 366-379, 2019
612019
Introduction to Moltres: an application for simulation of Molten Salt Reactors
A Lindsay, G Ridley, A Rykhlevskii, K Huff
Annals of Nuclear Energy 114, 530-540, 2018
442018
Whole core analysis of the single-fluid double-zone thorium molten salt reactor (SD-TMSR)
O Ashraf, A Rykhlevskii, GV Tikhomirov, KD Huff
Annals of Nuclear Energy 137, 107115, 2020
332020
Fuel cycle performance of fast spectrum molten salt reactor designs
A Rykhlevskii, BR Betzler, A Worrall, KD Huff
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019
282019
Deep learning approach to nuclear fuel transmutation in a fuel cycle simulator
JW Bae, A Rykhlevskii, G Chee, KD Huff
Annals of Nuclear Energy 139, 107230, 2020
252020
Strategies for thorium fuel cycle transition in the SD-TMSR
O Ashraf, A Rykhlevskii, GV Tikhomirov, KD Huff
Annals of Nuclear Energy 148, 107656, 2020
222020
Online Reprocessing Simulation for Thorium-Fueled Molten Salt Breeder Reactor
A Rykhlevskii, A Lindsay, K Huff
ANS Winter Meeting 2017 117, 239-242, 2017
82017
Full-Core Analysis of Thorium-Fueled Molten Salt Breeder Reactor Using the SERPENT 2 Monte Carlo Code
A Rykhlevskii, A Lindsay, K Huff
ANS Winter Meeting 2017 117, 239-242, 2017
82017
arfc/saltproc: Code for online reprocessing simulation of Molten Salt Reactor with external depletion solver SERPENT
A Rykhlevskii, JW Bae, K Huff
10.5281/zenodo.1196454, 2018
72018
Impacts of Fast-Spectrum Molten Salt Reactor Characteristics on Fuel Cycle Performance
BR Betzler, A Rykhlevskii, A Worrall, K Huff
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019
62019
Preliminary design of control rods in the single-fluid double-zone thorium molten salt reactor (SD-TMSR)
O Ashraf, A Rykhlevskii, GV Tikhomirov, KD Huff
Annals of Nuclear Energy 152, 108035, 2021
52021
Safety Analysis of Molten Salt Fast Reactor Fuel Composition using Moltres
SM Park, A Rykhlevskii, K Huff
Engineering Archive, 2019
42019
Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor
A Rykhlevskii
University of Illinois at Urbana-Champaign, 2018
42018
Fuel processing simulation tool for liquid-fueled nuclear reactors
A Rykhlevskii
University of Illinois at Urbana-Champaign, 2020
32020
Milestone 2.1 Report: Demonstration of SaltProc
A Rykhlevskii, K Huff
Milestone Report UIUC-ARFC-2019-04 DOI: 10.5281/zenodo. 3355649, University …, 2019
32019
The Impact of Xenon-135 on Load Following Transatomic Power Molten Salt Reactor
A Rykhlevskii, D O’Grady, T Kozlowski, K Huff
Department of Nuclear, Plasma, and Radiological Engineering, University of …, 2019
12019
Kairos power pebble bed reactor
A Rykhlevskii
Molten Salt Reactors and Thorium Energy, 945-952, 2024
2024
MITR & NBSR DDE Irradiations in BR2–Fluence in LEU Cladding and Structural Materials
A Rykhlevskii, A Bergeron, F Puig
Argonne National Lab.(ANL), Argonne, IL (United States), 2023
2023
Enabling Load Following Capability in the Transatomic Power MSR
J Chen, A Lee, C Brooks, K Huff, T Kozlowski, B Heuser, J Stubbins, ...
University of Illinois Urbana-Champaign, 2021
2021
Safety Analysis of the Molten Salt Fast Reactor Fuel Composition with Moltres
SM Park, A Rykhlevskii, KD Huff
Future 2, 31, 2019
2019
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