국제학술발표회 논문집
| No | Conference Name | Year | Subject Area | Title | Author | Paper File |
|---|---|---|---|---|---|---|
| 376 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Marduk: A Monte Carlo Code for Analyzing Stochastic Neutron Population Dynamics | Thomas M. Sutton, Andrew D. LaCharite, Anil K. Prinja (NNL) | PDF보기 |
| 377 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Neutron Clustering: Spatial Fluctuations In Multiplying Systems At The Critical Point | Andrea Zoia, Eric Dumonteil (CEA) | PDF보기 |
| 378 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Fixed-Source and Ex-Core Detector Calculations with SIMULATE5 | Tamer Bahadir, Matthew M. Giffen, Christopher Wells (Studsvik) | PDF보기 |
| 379 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Calculation of non-fundamental Modes in TRIVAC5 with SLEPc | A. Bernal, A. H챕bert, J.E. Roman, R. Mir처, G. Verd첬 (UPV) | PDF보기 |
| 380 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Analyses Supporting Design Review of TREAT Multi-SERTTA Experiment Test Vehicle | John D. Bess, Connie M. Hill, Nicolas E. Woolstenhulme, Colby B. Jensen(INL) | PDF보기 |
| 381 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Implementation of Molten Salt Reactor Neutronics Tools in SCALE | Benjamin R. Betzler, Jeffrey J. Powers, Nicholas R. Brown, Bradley T. Rearden (ORNL) | PDF보기 |
| 382 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | SCALE Multi-Group Libraries for Sodium-cooled Fast Reactor Systems | Friederike Bostelmann, Nicholas R. Brown, Andreas Pautz, Bradley T. Rearden, Kiril Velkov, Winfried Zwermann (GRS) | PDF보기 |
| 383 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Reduced Basis Element Method for Pin-by-Pin Calculations | Alexey L. Cherezov, Han G. Joo(SNU) | PDF보기 |
| 384 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Molten Salt Reactor Simulation Capability using MPACT | Benjamin Collins, Cole Gentry, Shane Stimpson(ORNL) | PDF보기 |
| 385 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | COCAGNE : EDF New Neutronic Core Code For Andromede Calculation Chain | Ansar Calloo, David Couyras, Fran챌ois F챕votte, Matthieu Guillo, Coline Brosselard, Bertrand Bouriquet, Alexandre Dubois, Fabrice Hoareau, Marie Fliscounakis, Hadrien Leroyer, Etienne Noblat, Yann Pora, Laurent Plagne, Ang챕lique Pon챌ot, Nadine Schwartz(EDF) | PDF보기 |
| 386 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | FEM-based Estimation of Reactivity Change due to Core Deformation in SFR | Woong Heo, Yonghee Kim (KAIST) | PDF보기 |
| 387 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Automate Multigroup Cross Section Library Verification Using Eigenvalue Analysis | Yuxuan Liu, Kaiwen Li(Michigan) | PDF보기 |
| 388 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | PARAGON2 Depletion Validation Using SERPENT Monte Carlo Code | Mohamed Ouisloumen(WEC) | PDF보기 |
| 389 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Accuracy and Runtime Improvements with SCALE 6.2 | Bradley T. Rearden, Benjamin R. Betzler, Matthew A. Jessee, William J. Marshall, Ugur Mertyurek, Mark L. Williams(ORNL) | PDF보기 |
| 390 | MC2017 | 2017 | General Reactor Analysis Methods and Applications | Introduction to the Nuclear Energy Advanced Modeling and Simulation Workbench | Bradley T. Rearden, Robert A. Lefebvre, Adam B. Thompson, Brandon R. Langley, Nicolas E. Stauff (ORNL) | PDF보기 |
Last Modified : 2023.11.20
