Search

Your search keyword '"William A. Wieselquist"' showing total 49 results

Search Constraints

Start Over You searched for: Author "William A. Wieselquist" Remove constraint Author: "William A. Wieselquist"
49 results on '"William A. Wieselquist"'

Search Results

1. Key nuclear data for non-LWR reactivity analysis

2. Neutronic Characteristics of ENDF/B-VIII.0 Compared to ENDF/B-VII.1 for Light-Water Reactor Analysis

3. Nuclear Data Sensitivity Study for the EBR-II Fast Reactor Benchmark Using SCALE with ENDF/B-VII.1 and ENDF/B-VIII.0

4. Data-Driven and Precursor-Group Uncertainty Propagation of Lattice Kinetic Parameters in UAM Benchmark

5. Modeling of the Molten Salt Reactor Experiment with SCALE

7. Secondary-Source Core Reload Modeling with VERA

8. Overview of the Tolerance Limit Calculations with Application to TSURFER

10. A new framework for sampling-based uncertainty quantification of the six-group reactor kinetic parameters

14. IMPROVEMENT OF SCALE-XSProc MULTIGROUP CROSS SECTION PROCESSING BASED ON THE CENTRM POINTWISE SLOWING DOWN CALCULATION

15. (α,n) nuclear data scoping study

18. Extension of SCALE/Sampler’s sensitivity analysis

19. Nuclide depletion capabilities in the Shift Monte Carlo code

20. VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion

21. Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON

27. Lattice physics calculations using the embedded self-shielding method in Polaris, Part I: Methods and implementation

28. Flux renormalization in constant power burnup calculations

29. SCALE capabilities for high temperature gas-cooled reactor analysis

30. Modeling and simulation of oxygen transport in high burnup LWR fuel

35. A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN

37. A cell-local finite difference discretization of the low-order quasidiffusion equations for neutral particle transport on unstructured quadrilateral meshes

38. Comparison of Two Approaches for Nuclear Data Uncertainty Propagation in MCNPX for Selected Fast Spectrum Critical Benchmarks

39. Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs

40. MPACT Standard Input User s Manual, Version 2.2.0

41. MPACT VERA Input User s Manual, Version 2.2.0

42. MPACT Theory Manual, Version 2.2.0

43. 5.0. Depletion, activation, and spent fuel source terms

44. ORIGAMI Automator Primer. Automated ORIGEN Source Terms and Spent Fuel Storage Pool Analysis

45. Status Report on NEAMS PROTEUS/ORIGEN Integration

46. Rod internal pressure quantification and distribution analysis using Frapcon

47. PSI Methodologies for Nuclear Data Uncertainty Propagation with CASMO-5M and MCNPX: Results for OECD/NEA UAM Benchmark Phase I

48. Nonlinear Projective-Iteration Methods for Solving Transport Problems on Regular and Unstructured Grids

49. One Validation Case of the CFD Software Fluent: Part of the Development Effort of a New Reactor Analysis Tool

Catalog

Books, media, physical & digital resources