Open Access
Issue
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
Article Number 15020
Number of page(s) 8
Section Sensitivity & Uncertainty Methods
DOI https://doi.org/10.1051/epjconf/202124715020
Published online 22 February 2021
  1. C. M. PERFETTI, B. T. REARDEN, and W. R. MARTIN, “SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations,” Nuclear Science and Engineering 182 (3), pp.332–353 (2016). [Google Scholar]
  2. M. AUFIERO et al., “A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT,” Annals of Nuclear Energy 85 June, pp.245–258 (2015). [Google Scholar]
  3. B. C. KIEDROWSKI and F. B. BROWN, “Adjoint-Based k -Eigenvalue Sensitivity Coefficients to Nuclear Data Using Continuous-Energy Monte Carlo,” Nuclear Science and Engineering 174 (3), pp.227–244 (2014). [Google Scholar]
  4. B. C. KIEDROWSKI, F. B. BROWN, and P. P. H. WILSON, “Adjoint-Weighted Tallies for k-Eigenvalue Calculations with Continuous-Energy Monte Carlo,” Nuclear Science and Engineering 168 (3), pp.226–241 (2011). [Google Scholar]
  5. X. PENG et al., “Development of continuous-energy sensitivity analysis capability in OpenMC,” Annals of Nuclear Energy 110, pp.362–383 (2017). [Google Scholar]
  6. C. BAKER et al., CALCULATING UNCERTAINTY ON K-EFFECTIVE WITH MONK10, in: ICNC 2015, Charlotte, NC, September 13-17 (2015). [Google Scholar]
  7. A. JINAPHANH, N. LECLAIRE, and B. COCHET, “Continuous-Energy Sensitivity Coefficients in the MORET Code,” Nuclear Science and Engineering 184 (1), pp.53–68 (2016). [Google Scholar]
  8. H. J. Shim and C. H. Kim, “Adjoint Sensitivity and Uncertainty Analyses in Monte Carlo Forward Calculations,” Journal of Nuclear Science and Technology 48 (12), pp.1453–1461 (2011). [Google Scholar]
  9. Y. QIU et al., “New strategies of sensitivity analysis capabilities in continuous-energy Monte Carlo code RMC,” Annals of Nuclear Energy 81, pp.50-61 (2015). [Google Scholar]
  10. Y. QIU et al., “Computing eigenvalue sensitivity coefficients to nuclear data by adjoint superhistory method and adjoint Wielandt method implemented in RMC code,” Annals of Nuclear Energy 87, pp.228-241 (2016). [Google Scholar]
  11. Y. QIU et al., “Computing eigenvalue sensitivity coefficients to nuclear data based on the CLUTCH method with RMC code,” Annals of Nuclear Energy 88, pp.237-251 (2016). [Google Scholar]
  12. Y. QIU, K. WANG, and J. YU, “Development of Sensitivity Analysis Capability in RMC code,” Transactions of the American Nuclear Society, Vol. 111, Anaheim, CA, November 9–13 (2014). [Google Scholar]
  13. Y. QIU et al., “Development of sensitivity analysis capabilities of generalized responses to nuclear data in Monte Carlo code RMC,” Annals of Nuclear Energy 97, pp.142-152 (2016). [Google Scholar]
  14. Y. QIU et al., “Generalized Sensitivity Analysis With Continuous-Energy Monte Carlo Code RMC,” in ICONE24, Charlotte, North Carolina (2016). [Google Scholar]
  15. C. M. PERFETTI and B. T. REARDEN, “A New Method for Calculating Generalized Response Sensitivities in Continuous-Energy Monte Carlo Applications in SCALE,” Transactions of the American Nuclear Society, Vol. 109, Washington, D.C., November 10–14 (2013). [Google Scholar]
  16. C. M. PERFETTI and B. T. REARDEN, “Development of a Generalized Perturbation Theory Method for Sensitivity Analysis Using Continuous-Energy Monte Carlo Methods,” Nuclear Science and Engineering 182 (3), pp.354–368 (2016). [Google Scholar]
  17. C. M. PERFETTI and B. T. REARDEN, “Performance Enhancements to the SCALE TSUNAMI-3D Generalized Response Sensitivity Capability,” Transactions of the American Nuclear Society, Vol. 111, Anaheim, California, November 9–13 (2014). [Google Scholar]
  18. G. SHI et al., “Development of Generalized Response Sensitivity Analysis Capability in RMC Code,” in M&C 2019, Portland, Oregon, USA. August 25-29, (2019). [Google Scholar]
  19. G. SHI et al., “Superhistory-based differential operator method for generalized responses sensitivity calculations,” Annals of Nuclear Energy 140, 107291, (2020). [Google Scholar]
  20. G. SHI et al., “Development of Superhistory-based GEAR-MC method for Generalized Responses,” in ICAPP 2020 Abu Dhabi-UAE. 15–19 March, (2020). [Google Scholar]
  21. G. SHI et al., “Improved Generalized Perturbation Theory Method for sensitivity analysis of generalized response function,” submitted to Progress in Nuclear Energy. [Google Scholar]
  22. T. P. BURKE and B. C. KIEDROWSKI, “Monte Carlo Perturbation Theory Estimates of Sensitivities to System Dimensions,” Nuclear Science and Engineering 189 (3), pp.199–223 (2018). [Google Scholar]
  23. K. F. RASKACH, “An Improvement of the Monte Carlo Generalized Differential Operator Method by Taking into Account First- and Second-Order Perturbations of Fission Source,” Nuclear Science and Engineering 162 (2), pp.158–166 (2009). [Google Scholar]
  24. International Handbook of Evaluated Criticality Safety Benchmarks Experiments. OECD Nuclear Energy Agency Nuclear Science Committee of the Organization for Economic Co-operation and Development (2011). [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.