43 results on '"Turinsky, Paul J."'
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2. Modeling and simulation challenges pursued by the Consortium for Advanced Simulation of Light Water Reactors (CASL)
3. Core Isotopic Depletion and Fuel Management
4. Advances in Nuclear Fuel Management for Light Water Reactors
5. User Guidelines and Best Practices for CASL VUQ Analysis Using Dakota
6. User Guidelines and Best Practices for CASL VUQ Analysis Using Dakota.
7. Non-linear, time dependent target accuracy assessment algorithm for multi-physics, high dimensional nuclear reactor calculations
8. Managing Model Data Introduced Uncertainties in Simulator Predictions for Generation IV Systems via Optimum Experimental Design
9. Preface to Shippingport Atomic Power Station thematic issue
10. Special issue on the “Consortium for Advanced Simulation of Light Water Reactors Research and Development Progress”
11. Extension des capacités du CASL : point d’étape
12. Advances in Nuclear Fuel Management for Light Water Reactors
13. Optimization of Thermal-Hydraulic Reactor System for SMRs via Data Assimilation and Uncertainty Quantification
14. Experiment Optimization to Reduce Nuclear Data Uncertainties in Support of Reactor Design
15. ADVANCES IN MULTI-PHYSICS AND HIGH PERFORMANCE COMPUTING IN SUPPORT OF NUCLEAR REACTOR POWER SYSTEMS MODELING AND SIMULATION
16. Efficient Subspace Methods-Based Algorithms for Performing Sensitivity, Uncertainty, and Adaptive Simulation of Large-Scale Computational Models
17. Adaptive Core Simulation Employing Discrete Inverse Theory - Part I: Theory
18. Nuclear Fuel Management Optimization: A Work in Progress
19. Adaptive Core Simulation Employing Discrete Inverse Theory - Part II: Numerical Experiments
20. Development and Implementation of a Newton-BICGSTAB Iterative Solver in the FORMOSA-B BWR Core Simulator Code
21. Super-Nodal Methods for Space-Time Kinetics
22. FORMOSA-P Three-Dimensional/Two-Dimensional Geometry Collapse Methodology
23. FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package III
24. FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package II
25. FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package
26. Higher Order Generalized Perturbation Theory for Boiling Water Reactor In-Core Fuel Management Optimization
27. Pressurized Water Reactor Core Maneuvering Utilizing Optimal Control Theory
28. Error Analysis of the Nodal Expansion Method for Solving the Neutron Diffusion Equation
29. A Second-Derivative-Based Adaptive Time-Step Method for Spatial Kinetics Calculations
30. Parallel Implementation of Integral Transport Methods
31. Employing Nodal Generalized Perturbation Theory for the Minimization of Feed Enrichment during Pressurized Water Reactor In-Core Nuclear Fuel Management Optimization
32. Application of Nonlinear Nodal Diffusion Generalized Perturbation Theory to Nuclear Fuel Reload Optimization
33. In-Core Nuclear Fuel Management Optimization for Pressurized Water Reactors Utilizing Simulated Annealing
34. Vectorized and Multitasked Solution of the Few-Group Neutron Diffusion Equations
35. Analytic Predictions of Boiling Film Stability for Conditions Consistent with Light Water Reactor Degraded Core Conditions
36. Automatic Determination of Pressurized Water Reactor Core Loading Patterns That Maximize Beginning-of-Cycle Reactivity Within Power-Peaking and Burnup Constraints
37. Authors
38. Authors
39. Out-of-Core Fuel Cycle Optimization for Nonequilibrium Cycles
40. The Degenerate Kernel Technique and Neutron Thermalization Calculations in Asymptotic Reactor Theory
41. Applications of the Degenerate Kernel Technique to Thermal Neutron Spectra Calculations
42. Master Of Nuclear Engineering Traineeship Program
43. The super-variational technique revisited
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