Open Access
| Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
|---|---|---|
| Article Number | 08013 | |
| Number of page(s) | 8 | |
| Section | Research Reactors and Facilities | |
| DOI | https://doi.org/10.1051/epjconf/202124708013 | |
| Published online | 22 February 2021 | |
- E. Losa, et al. “Simulations of Advanced Reactor Cores in Research Light Water Reactor LR-0.” Nuclear Engineering and Design, 342, pp. 205–09 (2019). [Google Scholar]
- E. Losa, et al. “Neutronic Experiments with Fluorine Rich Compounds at LR-0 Reactor.” Annals of Nuclear Energy, 120, pp. 286–95 (2018). [Google Scholar]
- M. Košťal, et al. “VVER-1000 Physics Experiments Hexagonal Lattices (1.275 cm Pitch) of Low Enriched U(3.3wt.% U235)O2 Fuel Assemblies in Light Water With Graphite and Fluoride Salt Insertions in Central Assembly,” LR(0)-VVER-RESR-003 CRIT-SPEC, NEA/NSC/DOC(2006)1. [Google Scholar]
- M. Koštal et al., “Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor,” Ann. Nucl. En., 87, (2016), 601–611. [Google Scholar]
- M. Koštal et al., “Measurement of various monitors reaction rate in a special core at LR-0 reactor,” Ann. Nucl. En., 112, (2018), 759–768. [Google Scholar]
- M. Koštal et al., “On similarity of various reactor spectra and 235U prompt fission neutron spectrum,” Appl. Rad. Isot., 135, (2018), 83–91. [Google Scholar]
- M. Koštal et al., “Determining the axial power profile of partly flooded fuel in a compact core assembled in reactor LR-0,” Ann. Nucl. En., 90, (2016), 450–458. [Google Scholar]
- A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets, in preparation [Google Scholar]
- C.J. Werner (editor), “MCNP Users Manual - Code Version 6.2,” LA-UR-17–29981, (2017). [Google Scholar]
- M.B. Chadwick et al. “ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology,” Nucl. Data Sheets, 107, (2006), 2931. [Google Scholar]
- J. Leppanen, et al. (2015) “The Serpent Monte Carlo code: Status, development and applications in 2013.” Ann. Nucl. Energy, 82 (2015) 142–150. [Google Scholar]
- A. Qualls et al. “Fluoride Salt-Cooled High-Temperature Demonstration Reactor Point Design,” research report ORNL/TM-2016/85, Oak Ridge National Laboratory, 2016. [Google Scholar]
- E. Losa et al. “Activation Rates Validation to Support MSR Development,” Transactions of the American Nuclear Society, 120, 921–922. [Google Scholar]
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