EDP Sciences logo
Web of Conferences logo
Search
Menu
All issues Volume 247 (2021) EPJ Web Conf., 247 (2021) 06019 References
Open Access
Issue
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
Article Number 06019
Number of page(s) 11
Section Advanced Modelling and Simulation
DOI https://doi.org/10.1051/epjconf/202124706019
Published online 22 February 2021
  1. W. C. Dawn. Simulation of Fast Reactors with the Finite Element Method and Multiphysics Models. Master’s thesis, North Carolina State University (2019). [Google Scholar]
  2. E. M. Gelbard. “Application of Spherical Harmonics Method to Reactor Problems.” Technical Report WAPD-BT-20, Bettis Atomic Power Laboratory (1960). [Google Scholar]
  3. K. S. Smith. “Multi-Dimensional Nodal Transport Using the Simplified PL Method.” In Proceedings of the Topical Meeting on Reactor Physics and Safety, NUREG/CP-0080, pp. 223–234. Saratoga Springs, NY (1986). [Google Scholar]
  4. E. W. Larsen, J. E. Morel, and J. M. McGhee. “Asymptotic Derivation of the Multigroup P1 and Simplified PN Equations with Anisotropic Scattering.” Nuclear Science and Engineering, volume 123, pp. 328–342 (1996). [Google Scholar]
  5. P. S. Brantley and E. W. Larsen. “The Simplified P3 Approximation.” Nuclear Science and Engineering, volume 134, pp. 1–21 (2000). [Google Scholar]
  6. S. Nakamura. Computational Methods in Engineering Science. Wiley, New York (1977). [Google Scholar]
  7. J. K. Fink and L. Leibowitz. “Thermodynamic and Transport Properties of Sodium Liquid and Vapor.” Technical Report ANL/RE-95/2, Argonne National Laboratory (1995). [Google Scholar]
  8. Y. S. Kim, T. W. Cho, and D. S. Sohn. “Thermal Conductivities of Actinides (U, Pu, Np, Cm, Am) and Uranium-Alloys (U-Zr, U-Pu-Zr and U-Pu-TRU-Zr).” Journal of Nuclear Materials, volume 445(1-3), pp. 272–280 (2014). [Google Scholar]
  9. W. Pfrang and D. Struwe. “Assessment of Correlations for Heat Transfer to the Coolant for Heavy Liquid Metal Cooled Core Designs.” Technical report, Forschungszentrum Karlsruhe GmbH, Karlsruhe (2007). FZKA 7352. [Google Scholar]
  10. P. A. Ushakov, A. V. Zhukov, and N. M. Matyukhin. “Heat Transfer to Liquid Metals in Regular Arrays of Fuel Elements.” Teplofizika Vysokikh Temperatur, volume 15, pp. 1027–1033 (1977). [Google Scholar]
  11. H. Planchon, J. Sackett, G. Golden, and R. Sevy. “Implications of the EBR-II Inherent Safety Demonstration Test.” Nuclear Engineering and Design, volume 101(1), pp. 75–90 (1987). [Google Scholar]
  12. L. Leibowitz and R. A. Blomquist. “Thermal Conductivity and Thermal Expansion of Stainless Steels D9 and HT9.” International Journal of Thermophysics, volume 9(5), pp. 873–883 (1988). [Google Scholar]
  13. C. Basak, G. Prasad, H. Kamath, and N. Prabhu. “An evaluation of the Properties of As-Cast U-Rich U–Zr Alloys.” Journal of Alloys and Compounds, volume 480(2), pp. 857–862 (2009). [Google Scholar]
  14. C. Fiorina, S. Radman, M.-Z. Koc, and A. Pautz. “Detailed Modeling fo the Thermal Expansion Reactivity Feedback in Fast Reactors Using OpenFOAM.” In Proceedings of M&C 2019, pp. 1434–1442. Portland, OR (2019). [Google Scholar]
  15. OECD Nuclear Energy Agency. “Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sized.” Technical report (2016). NEA/NSC/R(2015)9. [Google Scholar]
  16. C. H. Lee and W. S. Yang. “MC2-3: Multigroup Cross Section Generation Code for Fast Rector Analysis.” Nuclear Science and Engineering, volume 187, p. 268 (2017). [Google Scholar]
  17. R. A. Knief. Nuclear Engineering: Theory and Technology of Commerical Nuclear Power. American Nuclear Society, Inc., Lagrange Park, IL (2014). [Google Scholar]
  18. M. Pusa. Numerical Methods for Nuclear Fuel Burnup Calculations. Ph.D. thesis, Aalto University (2013). [Google Scholar]
  19. G. Chiba. “Effect of Neutron Anisotropic Scattering in Fast Reactor Analysis.” Transactions of the Atomic Energy Society of Japan, volume 3(2), pp. 200–207 (2004). [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.