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Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 1-29
Technical Paper / dx.doi.org/10.13182/NSE04-A2437
Calculating Probability Tables for the Unresolved-Resonance Region Using Monte Carlo Methods
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 30-42
Technical Paper / dx.doi.org/10.13182/NSE04-A2438
Statistical Assignment of Neutron Orbital Angular Momentum to a Resonance
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 43-49
Technical Paper / dx.doi.org/10.13182/NSE04-A2439
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 50-54
Technical Paper / dx.doi.org/10.13182/NSE04-A2440
On the Neutron Kinetics and Control of Accelerator-Driven Systems
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 55-66
Technical Paper / dx.doi.org/10.13182/NSE148-55
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 67-78
Technical Paper / dx.doi.org/10.13182/NSE04-A2442
Application of the Multipoint Method to the Kinetics of Accelerator-Driven Systems
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 79-88
Technical Paper / dx.doi.org/10.13182/NSE02-10D
Transport Effects for Source-Oscillated Problems in Subcritical Systems
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 89-102
Technical Paper / dx.doi.org/10.13182/NSE04-A2444
Neutronic Analyses of the Trade Demonstration Facility
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 103-123
Technical Paper / dx.doi.org/10.13182/NSE04-A2445
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 124-152
Technical Paper / dx.doi.org/10.13182/NSE01-13C
A Receding Horizon Controller with a Parameter Estimator for Nuclear Reactor Power Distribution
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 153-161
Technical Paper / dx.doi.org/10.13182/NSE04-A2447
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 162-171
Technical Paper / dx.doi.org/10.13182/NSE04-A2448
RTk/SN Solutions of the Two-Dimensional Multigroup Transport Equations in Hexagonal Geometry
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 172-185
Technical Paper / dx.doi.org/10.13182/NSE04-A2449
Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 186-194
Technical Paper / dx.doi.org/10.13182/NSE04-A2450
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 195-207
Technical Paper / dx.doi.org/10.13182/NSE04-A2451
Application of TRAC/BF1-ENTRÉE-NASCA to OECD NEA/NSC BWR Turbine Trip Benchmark
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 208-225
Technical Paper / dx.doi.org/10.13182/NSE04-A2452
Analysis of the Boiling Water Reactor Turbine Trip Benchmark with the Codes DYN3D and ATHLET/DYN3D
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 226-234
Technical Paper / dx.doi.org/10.13182/NSE04-A2453
Computation of a BWR Turbine Trip with CATHARE-CRONOS2-FLICA4 Coupled Codes
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 235-246
Technical Paper / dx.doi.org/10.13182/NSE04-A2454
OECD/NRC BWR Turbine Trip Benchmark: Simulation by POLCA-T Code
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 247-255
Technical Paper / dx.doi.org/10.13182/NSE04-A2455
Peach Bottom Transients Analysis with TRAC/BF1-VALKIN
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 256-269
Technical Paper / dx.doi.org/10.13182/NSE04-A2456
Analysis of the OECD/NRC BWR Turbine Trip Benchmark by the Coupled-Code System ATHLET-QUABOX/CUBBOX
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 270-280
Technical Paper / dx.doi.org/10.13182/NSE04-A2457
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 281-290
Technical Paper / dx.doi.org/10.13182/NSE04-A2458
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 291-305
Technical Paper / dx.doi.org/10.13182/NSE04-A2459
Peach Bottom BWR Turbine Trip Benchmark Analyses with RETRAN-3D and CORETRAN
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 306-324
Technical Paper / dx.doi.org/10.13182/NSE04-A2460
SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 325-336
Technical Paper / dx.doi.org/10.13182/NSE04-A2461
Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 337-353
Technical Paper / dx.doi.org/10.13182/NSE04-A2462
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 355-373
Technical Paper / dx.doi.org/10.13182/NSE03-12
Time Series Analysis of Monte Carlo Fission Sources—I: Dominance Ratio Computation
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 374-390
Technical Paper / dx.doi.org/10.13182/NSE03-95
Ex Post Facto Monte Carlo Variance Reduction
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 391-402
Technical Paper / dx.doi.org/10.13182/NSE04-A2465
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 403-413
Technical Paper / dx.doi.org/10.13182/NSE04-A2466
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 414-425
Technical Paper / dx.doi.org/10.13182/NSE04-A2467
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 426-428
Technical Paper / dx.doi.org/10.13182/NSE04-A2468
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 429-444
Technical Paper / dx.doi.org/10.13182/NSE04-A2469
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 445-452
Technical Paper / dx.doi.org/10.13182/NSE04-A2470
The Thermal Diffusion Length Problem in an Array of Plates
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 453-457
Technical Note / dx.doi.org/10.13182/NSE04-A2471
Resource Note on Photofission of Nuclei for 235U and 239Pu Detection
Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 458-461
Technical Note / dx.doi.org/10.13182/NSE04-A2472