Παρακολούθηση
Friederike Bostelmann
Friederike Bostelmann
Η διεύθυνση ηλεκτρονικού ταχυδρομείου έχει επαληθευτεί στον τομέα ornl.gov
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Παρατίθεται από
Παρατίθεται από
Έτος
Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
D Rochman, O Leray, M Hursin, H Ferroukhi, A Vasiliev, A Aures, ...
Nuclear Data Sheets 139, 1-76, 2017
642017
SCALE capabilities for high temperature gas-cooled reactor analysis
F Bostelmann, C Celik, ML Williams, RJ Ellis, G Ilas, WA Wieselquist
Annals of Nuclear Energy 147, 107673, 2020
362020
Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X
A Aures, F Bostelmann, M Hursin, O Leray
Annals of Nuclear Energy 101, 262-269, 2017
322017
Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE
F Bostelmann, G Strydom
Annals of Nuclear Energy 110, 317-329, 2017
292017
Modeling of the molten salt reactor experiment with SCALE
F Bostelmann, SE Skutnik, ED Walker, G Ilas, WA Wieselquist
Nuclear Technology 208 (4), 603-624, 2022
272022
SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis
R Bostelmann, C Celik, RF Kile, WA Wieselquist
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022
252022
Key nuclear data impacting reactivity in advanced reactors
F Bostelmann, G Ilas, WA Wieselquist
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020
232020
Two-step neutronics calculations with Shift and Griffin for advanced reactor systems
TM Pandya, F Bostelmann, M Jessee, J Ortensi
Annals of Nuclear Energy 173, 109131, 2022
222022
Nuclear data assessment for advanced reactors
R Bostelmann, G Ilas, C Celik, AM Holcomb, WA Wieselquist
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2021
212021
Uncertainty and sensitivity analysis in criticality calculations with perturbation theory and sampling
F Bostelmann, FP Weiß, A Aures, K Velkov, W Zwermann, BT Rearden, ...
Mathematics and Computations, Supercomputing in Nuclear Applications and …, 2015
212015
Criticality calculations of the very high temperature reactor critical assembly benchmark with serpent and SCALE/KENO-VI
F Bostelmann, HR Hammer, J Ortensi, G Strydom, K Velkov, W Zwermann
Annals of Nuclear Energy 90, 343-352, 2016
192016
Sampling-based nuclear data uncertainty analysis in criticality and depletion calculations
F Bostelmann, W Zwermann, B Krzykacz-Hausmann, L Galiner, A Aures, ...
Mathematics and Computations, Supercomputing in Nuclear Applications and …, 2015
192015
Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors
F Bostelmann, AM Holcomb, JB Clarity, WBJ Marshall, V Sobes, ...
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019
172019
Assessment of SCALE and MELCOR for a generic pebble bed fluoride high-temperature reactor
RF Kile, F Bostelmann, SE Skutnik, WA Wieselquist, NR Brown
Annals of Nuclear Energy 173, 109107, 2022
162022
Reactor simulations with nuclear data uncertainties
A Aures, W Bernnat, F Bostelmann, J Bousquet, B Krzykacz-Hausmann, ...
Nuclear Engineering and Design 355, 110313, 2019
162019
The IAEA coordinated research programme on HTGR uncertainty analysis: Phase I status and Ex. I-1 prismatic reference results
F Bostelmann, G Strydom, F Reitsma, K Ivanov
Nuclear Engineering and Design 306, 77-88, 2016
162016
Results for Phase I of the IAEA coordinated research program on HTGR uncertainties
G Strydom, F Bostelmann, SJ Yoon
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2015
162015
The IAEA coordinated research program on HTGR uncertainty analysis: phase I status and initial results
F Reitsma, G Strydom, F Bostelmann, K Ivanov
Proceedings of HTR, 2014
162014
Extension of SCALE/Sampler’s sensitivity analysis
F Bostelmann, D Wiarda, G Arbanas, WA Wieselquist
Annals of Nuclear Energy 165, 108641, 2022
152022
Objectives and Status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM)
G Rimpault, L Buiron, N Stauff, TK Kim, TA Taiwo, YK Lee, A Aures, ...
International Conference on Fast Reactors and Related Fuel Cycles (FR-2017), 2017
152017
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