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Shane Stimpson
Shane Stimpson
Verified email at ornl.gov
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Cited by
Cited by
Year
Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT
B Collins, S Stimpson, BW Kelley, MTH Young, B Kochunas, A Graham, ...
Journal of Computational Physics 326, 612-628, 2016
1872016
VERA core simulator methodology for pressurized water reactor cycle depletion
B Kochunas, B Collins, S Stimpson, R Salko, D Jabaay, A Graham, Y Liu, ...
Nuclear Science and Engineering 185 (1), 217-231, 2017
1202017
VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12
A Godfrey, B Collins, KS Kim, J Powers, R Salko, S Stimpson, ...
Physics of Reactors 2016: Unifying Theory and Experiments in the 21st …, 2016
522016
Axial transport solvers for the 2D/1D scheme in MPACT
SG Stimpson, BS Collins, TJ Downar
352015
Assessment of 2D/1D Capability in MPACT
B Collins, S Stimpson, B Kochunas, T Downar, W Martin
Proc. PHYSOR 2014, 2014
34*2014
VERA core simulator methodology for PWR cycle depletion
B Kochunas, BS Collins, D Jabaay, KS Kim, A Graham, S Stimpson, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Oak Ridge …, 2015
322015
Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3
S Stimpson, J Powers, K Clarno, R Pawlowski, R Gardner, S Novascone, ...
Nuclear Engineering and Design 327, 172-186, 2018
312018
Improvement of transport-corrected scattering stability and performance using a Jacobi inscatter algorithm for 2D-MOC
S Stimpson, B Collins, B Kochunas
Annals of Nuclear Energy 105, 1-10, 2017
282017
An Azimuthal, Fourier Moment-Based Axial SN Solver for the 2D/1D Scheme.
SG Stimpson
262015
A 2-D/1-D transverse leakage approximation based on azimuthal, fourier moments
S Stimpson, B Collins, T Downar
Nuclear Science and Engineering 185 (2), 243-262, 2017
242017
Subplane collision probabilities method applied to control rod cusping in 2D/1D
A Graham, B Collins, S Stimpson, T Downar
Annals of Nuclear Energy 118, 1-14, 2018
222018
Watts bar unit 2 startup results with vera
AT Godfrey, BS Collins, CA Gentry, SG Stimpson, JA Ritchie
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Consortium for …, 2017
212017
Mpact theory manual
B Collins, T Downar, J Gehin, A Godfrey, A Graham, D Jabaay, B Kelley, ...
Technical Report CASL-U-2015-0078-000, Consortium for Advanced Simulation of …, 2015
21*2015
Simulation of the BEAVRS benchmark using VERA
B Collins, A Godfrey, S Stimpson, S Palmtag
Annals of Nuclear Energy 145, 107602, 2020
202020
Coupled full core neutron transport/CFD simulations of pressurized water reactors
B Kochunas, S Stimpson, B Collins, T Downar, R Brewster, E Baglietto, ...
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park …, 2012
192012
Molten salt reactor fuel depletion tools in SCALE
BR Betzler, KB Bekar, W Wieselquist, SW Hart, SG Stimpson
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019
172019
AP1000® PWR startup core modeling and simulation with VERA-CS
F Franceschini, AT Godfrey, S Stimpson, T Evans, B Collins, JC Gehin, ...
5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015, 241-252, 2015
162015
Assessment of the analysis capability for core-wide PWR pellet-clad interaction screening of Watts Bar Unit 1
N Capps, S Stimpson, K Clarno, BD Wirth, J Rashid
Nuclear Engineering and Design 333, 131-144, 2018
142018
Coupled fuel performance calculations in VERA and demonstration on Watts Bar unit 1, cycle 1
S Stimpson, K Clarno, R Pawlowski, R Gardner, J Powers, B Collins, ...
Annals of Nuclear Energy 145, 107554, 2020
132020
Acceleration methods for whole core reactor simulations using VERA
B Collins, S Stimpson
Trans. Am. Nucl. Soc 118, 929, 2018
132018
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Articles 1–20