Open Access
Numéro |
EPJ Web Conf.
Volume 253, 2021
ANIMMA 2021 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications
|
|
---|---|---|
Numéro d'article | 07012 | |
Nombre de pages | 5 | |
Section | Nuclear Fuel Cycle, Safeguards and Homeland Security | |
DOI | https://doi.org/10.1051/epjconf/202125307012 | |
Publié en ligne | 19 novembre 2021 |
- J. Závorka, M. Lovecký, and R. Škoda, “Basic design of the TEPLATOR core construction” in Proc. 29th International Conference Nuclear Energy for New Europe (NENE 2020). Ljubljana: Nuclear Society of Slovenia, 2020. s. 402.1-402.7. ISBN 978-961-6207-49-2. [Google Scholar]
- T. Peltan, E. Vilímová, and R. Škoda, “Natural uranium as alternative fuel for TEPLATOR”. in: Proc. 29th International Conference Nuclear Energy for New Europe (NENE 2020). Ljubljana: Nuclear Society of Slovenia, 2020. s. 406.1-406.8. ISBN 978-961-6207-49-2. [Google Scholar]
- Special coolant displacer in nuclear fuel mitigating LOCA accident, by T. Peltan, E. Vilímová, R. Škoda (2020, March 20). Patent: PV 2020498 [Google Scholar]
- J. Leppänen, M. Pusa, T. Viitanen, V. Valtavirta, and T. Kaltiaisenaho, “The Serpent Monte Carlo code: Status, development and applications in 2013, ” Ann. Nucl. Energy, vol. 82, pp. 142–150, 2015, doi: 10.1016/j.anucene.2014.08.024. [Google Scholar]
- M. B. Chadwick et al., “ENDF/B-VII.1: Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data, ” Nucl. Data Sheets, vol. 112, 2011. [Google Scholar]
- L. H. Ortega, B. Blamer, K. M. Stern, J. Vollmer, S. M. McDeavitt, “Thermal conductivity of uranium metal and uranium-zirconium alloys fabricated via powder metallurgy” Jour. of Nucl. Materials, Vol. 531, 2020, ISSN 0022-3115, doi: 10.1016/j.jnucmat.2019.151982. [Google Scholar]
- B. Rouben, “CANDU Fuel-Management Course” Atomic Energy of Canada Ltd. [Google Scholar]