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Olin W Calvin
Olin W Calvin
PhD Student, University of Idaho
Verified email at vandals.uidaho.edu
Title
Cited by
Cited by
Year
Griffin user manual
M DeHart, FN Gleicher, V Laboure, J Ortensi, Z Prince, S Schunert, ...
INL/EXT-19-54247, 2020
112020
MAMMOTH Theory Manual
M DeHart, F Gleicher, V Labouré, J Ortensi, S Schunert, Y Wang, O Calvin, ...
INL/EXT-19-54252, 2019
102019
Global error analysis of the Chebyshev rational approximation method
O Calvin, S Schunert, B Ganapol
Annals of Nuclear Energy 150, 107828, 2021
82021
An equilibrium core depletion algorithm for pebble-bed reactors in the Griffin code
S Schunert, J Ortensi, Y Wang, P Balestra, M Jaradat, O Calvin, ...
Annals of Nuclear Energy 192, 109980, 2023
72023
Implementation of isotopic removal capability in Griffin for multi-region MSR depletion analysis
SA Walker, A Abou Jaoude, OW Calvin, ME Tano Retamales
Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2022
62022
Improvements in High Temperature Gas Cooled Reactor Modeling Capabilities in the Pronghorn Code
S Schunert, MK Mohammad Jaradat, OW Calvin, GL Giudicelli, ...
Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2022
62022
Introduction of the Adding and Doubling Method for Solving Bateman Equations for Nuclear Fuel Depletion
OW Calvin, BD Ganapol, RA Borrelli
Nuclear Science and Engineering 197 (4), 558-588, 2023
42023
Implementation of Depletion Architecture in the MAMMOTH Reactor Physics Application
OW Calvin, MD DeHart, J Ortensi, S Schunert, Y Wang, S Goluoglu
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019
42019
Depletion chain simplification using pseudo-nuclides
O Calvin
Annals of Nuclear Energy 193, 110011, 2023
32023
Depletion-driven thermochemistry of molten salt reactors: review, method, and analysis
SA Walker, ME Tano, A Abou-Jaoude, O Calvin
Frontiers in Nuclear Engineering 2, 1214727, 2023
32023
Evaluating quantities of interest other than nuclide densities in the bateman equations
OW Calvin, MD Gale, S Schunert
Nuclear Science and Engineering 197 (8), 2234-2250, 2023
22023
Using Griffin's Transmutation Solver to Calculate Radiation Damage
MD Gale, S Schunert, OW Calvin
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2022
22022
Architecture Improvements and Retesting of the Microscopic Depletion Implementation in the MAMMOTH Reactor Physics Application
O Calvin, J Ortensi, Y Wang, S Schunert, S Goluoglu, MD DeHart
Idaho National Lab.(INL), Idaho Falls, ID (United States); Univ. of Florida …, 2019
22019
Application of the Gauss-Seidel Method to the Chebyshev Rational Approximation Method for Solving Nuclear Fuel Depletion Systems
OW Calvin, N Choi
Nuclear Science and Engineering, 1-21, 2023
12023
Multigroup cross section generation capability in GRIFFIN
H Park, C Lee, YS Jung, Y Wang, O Calvin, J Ortensi
American Nuclear Society-ANS, La Grange Park, IL 60526 (United States), 2022
12022
Cross Section Generation Capability in Griffin
H Park, C Lee, YS Jung, Y Wang, O Calvin, J Ortensi
Argonne National Lab.(ANL), Argonne, IL (United States); Idaho National Lab …, 2021
12021
Depletion Chain Simplification With Pseudo-Nuclides to Model Decay Effects
OW Calvin
University of Idaho, 2023
2023
Calculating Radiation Damage (DPA) from Transmutation Products
MD Gale, S Schunert, A Mata Cruz, OW Calvin, DJ Vanwasshenova
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2022
2022
Griffin-m
J Ortensi, Y Wang, JT Hanophy, S Schunert, ZM Prince, OW Calvin, ...
Idaho National Laboratory (INL), Idaho Falls, ID (United States); Argonne …, 2021
2021
Architecture for the Performance of Nuclear Fuel Depletion Calculations
OW Calvin, MD DeHart
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019
2019
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