Active Filters

  • (-) PSI Groups = 4105 Schnellereaktoren
  • (-) Keywords ≠ PARCS
Search Results 1 - 20 of 121

Pages

  • RSS Feed
Select Page
Statistical burnup distribution of moving pebbles in the HTR-PM reactor
Vitullo, F., Krepel, J., Kalilainen, J., Prasser, H. M., & Pautz, A. (2020). Statistical burnup distribution of moving pebbles in the HTR-PM reactor. Journal of Nuclear Engineering and Radiation Science, 6(2), 021108 (14 pp.). https://doi.org/10.1115/1.4044910
Conclusions of a benchmark study on the EBR-II SHRT-45R experiment
Bates, E., Zhang, D., Truong, B., Sui, D., Hu, W., Su, G. H., … Mikityuk, K. (2018). Conclusions of a benchmark study on the EBR-II SHRT-45R experiment. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 372 (10 pp.). International Atomic Energy Agency.
IAEA's coordinated research project on EBR-II shutdown heat removal tests: an overview
Batra, C., Kriventsev, V., Monti, S., Briggs, L., Hu, W., Sui, D., … Bates, E. (2018). IAEA's coordinated research project on EBR-II shutdown heat removal tests: an overview. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 361 (8 pp.). International Atomic Energy Agency.
Benchmark analyses of EBR-II shutdown heat removal tests
Briggs, L., Kriventsev, V., Monti, S., Hu, W., Sui, D., Su, G., … Truong, B. (2018). Benchmark analyses of EBR-II shutdown heat removal tests. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 004 (10 pp.). International Atomic Energy Agency.
PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K
Chionis, D., Dokhane, A., Ferroukhi, H., Girardin, G., & Pautz, A. (2018). PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K. In Proceedings of the PHYSOR 2018 (pp. 1001-1012). American Nuclear Society.
On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors
Hombourger, B., Krepel, J., Mikityuk, K., & Pautz, A. (2018). On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 388 (11 pp.). International Atomic Energy Agency.
Comparison of fast reactors performance in the closed U-Pu and Th-U cycle
Krepel, J. (2018). Comparison of fast reactors performance in the closed U-Pu and Th-U cycle. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 052 (10 pp.). International Atomic Energy Agency.
Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow
Mambelli, S., Mikityuk, K., & Panadero, A. L. (2018). Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 451 (9 pp.). International Atomic Energy Agency.
ESFR-SMART: new Horizon-2020 project on SFR safety
Mikityuk, K., Girardi, E., Krepel, J., Bubelis, E., Fridman, E., Rineiski, A., … Garnier, J. C. (2018). ESFR-SMART: new Horizon-2020 project on SFR safety. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 450 (10 pp.). International Atomic Energy Agency.
GEN IV education and training initiative via public webinars
Paviet, P., Alekseev, P., Fazio, C., Fratoni, M., Hwang, I., Kelly, J., … Sun, J. (2018). GEN IV education and training initiative via public webinars. In Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 009 (8 pp.). International Atomic Energy Agency.
Low-void-effect sodium-cooled core: uncertainty of local sodium void reactivity as a result of nuclear data uncertainties
Pelloni, S., Panadero, A. L., Mikityuk, K., & Pautz, A. (2018). Low-void-effect sodium-cooled core: uncertainty of local sodium void reactivity as a result of nuclear data uncertainties. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 050 (10 pp.). International Atomic Energy Agency.
Objectives and status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM)
Rimpault, G., Buiron, L., Stauff, N. E., Kim, T. K., Taiwo, T. A., Lee, Y. K., … Ivanova, T. (2018). Objectives and status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM). In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 220 (13 pp.). International Atomic Energy Agency.
Statistical burnup distribution of moving pebbles in HTR-PM reactor
Vitullo, F., Krepel, J., Kalilainen, J., Prasser, H. M., & Pautz, A. (2018). Statistical burnup distribution of moving pebbles in HTR-PM reactor. In Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student Paper Competition (pp. ICONE26-81082 (10 pp.). https://doi.org/10.1115/ICONE26-81082
System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions
Bubelis, E., Tosello, A., Pfrang, W., Schikorr, M., Mikityuk, K., Panadero, A. L., … Wallenius, J. (2017). System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions. Nuclear Engineering and Design, 320, 325-345. https://doi.org/10.1016/j.nucengdes.2017.06.015
Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like sodium fast reactor
García-Herranz, N., Panadero, A. L., Martinez, A., Pelloni, S., Mikityuk, K., & Pautz, A. (2017). Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like sodium fast reactor. In A. Plompen, F. J. Hambsch, P. Schillebeeckx, W. Mondelaers, J. Heyse, S. Kopecky, … S. Oberstedt (Eds.), EPJ web of conferences: Vol. 146. ND 2016: international conference on nuclear data for science and technology (p. 09006 (6 pp.). https://doi.org/10.1051/epjconf/201714609006
Comparison of progressive incremental adjustment sequences for cross-section and variance/covariance data adjustment by analyzing fast-spectrum systems
Pelloni, S. (2017). Comparison of progressive incremental adjustment sequences for cross-section and variance/covariance data adjustment by analyzing fast-spectrum systems. Annals of Nuclear Energy, 106, 33-50. https://doi.org/10.1016/j.anucene.2017.03.040
Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels
Brankov, V., Khvostov, G., Mikityuk, K., Pautz, A., Restani, R., Abolhassani, S., … Wiesenack, W. (2016). Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels. Nuclear Engineering and Design, 305, 559-568. https://doi.org/10.1016/j.nucengdes.2016.06.021
Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data
Brankov, V., Khvostov, G., Mikityuk, K., Pautz, A., & Wiesenack, W. (2016). Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data. Nuclear Engineering and Design, 300, 97-106. https://doi.org/10.1016/j.nucengdes.2015.11.023
Full core LOCA analysis for BWR/6 - methodology and first results
Cozzo, C., Epiney, A., Canepa, S., Ferroukhi, H., Zerkak, O., Khvostov, G., … Gorzel, A. (2016). Full core LOCA analysis for BWR/6 - methodology and first results. In Top Fuel 2016. LWR fuels with enhanced safety and performance (pp. 1135-1144). American Nuclear Society.
The proto-Earth geo-reactor: a thorium reactor?
Degueldre, C., & Fiorina, C. (2016). The proto-Earth geo-reactor: a thorium reactor? In J. P. Revol, M. Bourquin, Y. Kadi, E. Lillestol, J. C. de Mestral, & K. Samec (Eds.), Thorium energy for the world. Proceedings of the ThEC13 conference, CERN, globe of science and innovation, Geneva, Switzerland, October 27-31, 2013 (pp. 415-416). https://doi.org/10.1007/978-3-319-26542-1
 

Pages