All Stories

  1. Experimental analyses of βeff/Λ in accelerator-driven system at Kyoto University Critical Assembly
  2. Nuclear data-induced uncertainty quantification of prompt neutron decay constant based on perturbation theory for ADS experiments at KUCA
  3. Real-time subcriticality monitoring system based on a highly sensitive optical fiber detector in an accelerator-driven system at the Kyoto University Critical Assembly
  4. Numerical benchmark problem of solid-moderated enriched-uranium-loaded core at Kyoto university critical assembly
  5. Transport consistent diffusion coefficient for CMFD acceleration and comparison of convergence properties
  6. First nuclear transmutation of 237Np and 241Am by accelerator-driven system at Kyoto University Critical Assembly
  7. A simple treatment of increased gap due to fuel assembly bowing through correction of cross sections
  8. A New Interpretation of Discontinuity Factor
  9. Experimental validation of unique combination numbers for third- and fourth-order neutron correlation factors of zero-power reactor noise
  10. Inverse estimation methods of unknown radioactive source for fuel debris search
  11. Comparison of theoretical formulae and bootstrap method for statistical error estimation of Feynman-α method
  12. Utilization of Regionwise Even-Parity Discontinuity Factor to Reduce Discretization Error of MOC
  13. Underestimation of statistical uncertainty of local tallies in Monte Carlo eigenvalue calculation for simple and LWR lattice geometries
  14. Flux Region Assignment Method Using Ray Trace Information for the Method of Characteristics to Improve Cache Efficiency
  15. Sensitivity analysis of prompt neutron decay constant using perturbation theory
  16. Estimation of sensitivity coefficient based on lasso-type penalized linear regression
  17. Uncertainty quantification of criticality in solid-moderated and -reflected cores at Kyoto University Critical Assembly
  18. Experimental analysis and uncertainty quantification using random sampling technique for ADS experiments at KUCA
  19. Analysis of the KUCA ADS benchmarks with diffusion theory
  20. Benchmarks of subcriticality in accelerator-driven system at Kyoto University Critical Assembly
  21. Recent developments in the GENESIS code based on the Legendre polynomial expansion of angular flux method
  22. Experimental benchmarks on kinetic parameters in accelerator-driven system with 100 MeV protons at Kyoto University Critical Assembly
  23. Automated generation of burnup chain for reactor analysis applications
  24. GENESIS: A Three-Dimensional Heterogeneous Transport Solver Based on the Legendre Polynomial Expansion of Angular Flux Method
  25. Estimation of sensitivity coefficients of core characteristics based on reduced-order modeling using sensitivity matrix of assembly characteristics
  26. Estimation of modeling approximation errors using data assimilation with the minimum variance approach
  27. On prediction accuracy of neutronics parameters of accelerator-driven system
  28. A CMFD Acceleration Method for SP3 Advanced Nodal Method
  29. An efficient execution of Monte Carlo simulation based on delta-tracking method using GPUs
  30. Discontinuity Factors for Simplified P3 Theory
  31. Reduction of MOC discretization errors through a minimization of source ratio variances
  32. Nuclear data-induced uncertainty quantification of neutronics parameters of accelerator-driven system
  33. Bias factor method using random sampling technique
  34. Statistical error estimation of the Feynman-α method using the bootstrap method
  35. Uncertainty Quantification of LWR Core Characteristics Using Random Sampling Method
  36. Confidence interval estimation by bootstrap method for uncertainty quantification using random sampling method
  37. Application of correction technique using leakage index combined with SPH or discontinuity factors for energy collapsing on pin-by-pin BWR core analysis
  38. Applicability of angular flux discontinuity factor preserving region-wise leakage for integro-differential transport equation
  39. A new technique for spectral interference correction on pin-by-pin BWR core analysis
  40. Cross section adjustment method based on random sampling technique
  41. Application of Augmented Reality to Nuclear Reactor Core Simulation for Fundamental Nuclear Engineering Education
  42. Evaluation of Higher Order Mode Components of Fission Source Distribution in Mote-Carlo Calculation
  43. A macroscopic cross-section model for BWR pin-by-pin core analysis
  44. Uncertainty estimation of core safety parameters using cross-correlations of covariance matrix
  45. Preservation of transmission probabilities in the method of characteristics
  46. Convergence analysis of MOC inner iterations with large negative self-scattering cross-section
  47. Analysis of integral experiment on erbia-loaded thermal spectrum cores using Kyoto University Critical Assembly by MCNP code with various cross section libraries
  48. An optimization approach to establish an appropriate energy group structure for BWR pin-by-pin core analysis
  49. A unified approach for numerical calculation of space-dependent kinetic equation
  50. Application of Quick Subchannel Analysis Method for Three-Dimensional Pin-by-Pin BWR Core Calculations
  51. Detected-neutron multiplication factor measured by neutron source multiplication method
  52. Application of the Robust Design Concept for Fuel Loading Pattern
  53. Improved Derivation of Multigroup Effective Cross Section for Heterogeneous System by Equivalence Theory
  54. Resonance Calculation for Large and Complicated Geometry Using Tone's Method by Incorporating the Method of Characteristics
  55. Explicit Time Integration Scheme Using Krylov Subspace Method for Reactor Kinetics Equation
  56. Improvement of Tone's Method with Two-Term Rational Approximation
  57. AEGIS: AN ADVANCED LATTICE PHYSICS CODE FOR LIGHT WATER REACTOR ANALYSES
  58. Verification and Validation of AEGIS/SCOPE2: The State-of-the-Art In-Core Fuel Management System for PWRs
  59. Development of deterministic code based on the discrete ordinates method for the third-order neutron correlation technique
  60. Development of New Solid Angle Quadrature Sets to Satisfy Even- and Odd-Moment Conditions
  61. Neutron Transport Models of AEGIS: An Advanced Next-Generation Neutronics Design System
  62. Effect of error propagation of nuclide number densities on Monte Carlo burn-up calculations
  63. Derivation of theoretical formula for the third order neutron correlation technique by using importance function
  64. Space and energy dependent theoretical formula for the third order neutron correlation technique