Open Access
| Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
|---|---|---|
| Article Number | 10016 | |
| Number of page(s) | 8 | |
| Section | Verification & Validation | |
| DOI | https://doi.org/10.1051/epjconf/202124710016 | |
| Published online | 22 February 2021 | |
- MPACT: User’s Manual, Version 1.0.0, November 8, 2013. [Google Scholar]
- “Consortium for Advanced Simulation of Light Water Reactors,” http://www.casl.gov/ (2015). [Google Scholar]
- J. Turner et al., “The Virtual Environment for Reactor Applications (VERA): Design and architecture,” J. Comput. Phys., 326(1), pp. 544–568 (2016). [Google Scholar]
- J. Y. Cho, H. G. Joo, K. S. Kim, S. Q. Zee, “Cell Based CMFD Formulation for Acceleration of Whole-core Method of Characteristics Calculation,” J. Korean Nucl. Soc., 34(3), pp. 250–258 (2002). [Google Scholar]
- “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation,” ORNL-TM/2005/39, Version 6.2, Oak Ridge National Laboratory, Oak Ridge, TN, USA (2016). (Available from the Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-834.) [Google Scholar]
- A. Khairallah, J. Recolin, “Calcul de l’autoprotection résonnante dans les cellules complexes par la méthode des sous-groupes,” Proc. Seminar IAEA-SM-154 on Numerical Reactor Calculations, pp. 305–317, IAEA, Vienna (1972). [Google Scholar]
- M. L. Williams, K. S. Kim, “The Embedded Self-Shielding Method,” PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education, Knoxville, TN, USA, April 15–20, 2012 (2012). [Google Scholar]
- K. S. Kim, M. L. Williams, D. Wiarda, K. T. Clarno, “Development of the Multigroup Cross Section Library for the CASL Neutronics Simulator MPACT: Method and Procedure,” Ann. Nucl. Energ., 133, pp. 46–58 (2019). [Google Scholar]
- K. S. Kim, M. L. Williams, A. Holcomb, D. Wiarda, B. K. Jeon, W. S. Yang, “The SCALE/AMPX Multigroup Cross Section Processing for Fast Reactor Analysis,” Ann. Nucl. Energ., 132, pp. 161–171 (2019). [Google Scholar]
- B. R. Herman, B. Forget, K. Smith, “Improved Diffusion Coefficients Generated from Monte Carlo Codes,” 2013 Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, ID, USA, May 5–9, 2013 (2013). [Google Scholar]
- S. E. Jensen, E. Nonbol, “Description of the Magnox Type of Gas Cooled Reactor (MAGNOX),” NKS-2 ISBN 87-7893-050-2, Riso National Laboratory, Roskilde, Denmark (1999). [Google Scholar]
- N. P. Luciano, B. J. Ade, K. S. Kim, “Verification of MPACT using Magnox Reactor Neutronics Progression Problems,” (forthcoming) PHYSOR 2020, Cambridge, United Kingdom, March 29–April 2, 2020 (2020). [Google Scholar]
- K. S. Kim et al., “Development of a Physics Analysis Procedure for the Prismatic Very High Temperature Gas Cooled Reactors,” Ann. Nucl. Energ., 34(11), pp. 849–860 (2007). [Google Scholar]
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.