Open Access
Issue
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
Article Number 20003
Number of page(s) 9
Section Global Nuclear Innovation (Special session)
DOI https://doi.org/10.1051/epjconf/202124720003
Published online 22 February 2021
  1. M. Hone et al., AP1000 Core Reference Report, Westinghouse Electric Company, March 2012 WCAP-17524-NP [Google Scholar]
  2. T. Morita, et al., “Application of MSHIM Core Control Strategy for Westinghouse AP1000 Nuclear Power Plant”, International conference on global environment and advanced nuclear power plants GENES4/ANP2003; Kyoto (Japan); 15-19 Sep 2003. [Google Scholar]
  3. K. Drudy, etc., Robustness of the MSHIM Operation and Control Strategy in the AP1000 Design, 17th International Conference on Nuclear Engineering (ICONE 17), July 12-16, 2009, Brussels, Belgium [Google Scholar]
  4. B. Kochunas, et al., “VERA Core Simulator Methodology for PWR Core Cycle Depletion,” Nucl. Sci. and Eng., 185(1), 2017. [Google Scholar]
  5. B. Kochunas, et al., “Overview of Development and Design of MPACT: Michigan Parallel Characteristics Transport Code,” Proc. Int. Conf. M&C 2013, ANS, Sun Valley, ID, USA. May 5-9 (2013). [Google Scholar]
  6. I. C. Gauld, O. W. Hermann, and R. M. Westfall, “ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms,” NUREG/CR-0200, Revision 7, Volume 2, Section F7, ORNL/NUREG/CSD-2/V2/R7 (2002) [Google Scholar]
  7. R. Salko M. Avramova, “CTF Theory Manual”, North Carolina State University (2017). [Google Scholar]
  8. T. M. Pandya, S. R. Johnson, T. M. Evans, G. G. Davidson, S. P. Hamilton, A. T. Godfrey, “Implementation, capabilities, and benchmarking of Shift, a massively parallel Monte Carlo radiation transport code”, Journal of Computational Physics 308 (2016) 239–272. [Google Scholar]
  9. F. Franceschini et. al., AP1000® PWR Reactor Physics Analysis with VERA-CS and KENO-VI – Part I: Zero Power Physics Tests”, PHYSOR 2014 – The Role of Reactor Physics Toward a Sustainable Future, Kyoto (Japan), September 28 – October 3, 2014 [Google Scholar]
  10. F. Franceschini et. al., AP1000® PWR Reactor Physics Analysis with VERA-CS and KENO-VI – Part II: Power Distribution”, PHYSOR 2014 – The Role of Reactor Physics Toward a Sustainable Future, Kyoto (Japan), September 28 – October 3, 2014 [Google Scholar]
  11. F. Franceschini et. al., AP1000 PWR Startup Core Simulations with VERA-CS”, Advances in Nuclear Fuel Management V (ANFM 2015), Hilton Head Island, South Carolina, (USA) March 29-April 1, 2015 [Google Scholar]
  12. D. Salazar et. al., “AP1000 PWR Cycle 1 HFP Depletion Simulations with VERA-CS”, PHYSOR2016 - Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho (USA) May 1-5, 2016 [Google Scholar]
  13. M.E. Dunn and N.M. Greene, “AMPX-2000: A Cross section Processing System for Generating Nuclear Data for Criticality Safety Applications,” Trans. Am. Nucl. Soc. 86, 118–119 (2002). [Google Scholar]

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