Number 1 | Number 2 | Number 3
Error Estimations and Their Biases in Monte Carlo Eigenvalue Calculations
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 1-11
Technical Paper / dx.doi.org/10.13182/NSE97-1
Post-Convergence Automatic Differentiation of Iterative Schemes
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 12-18
Technical Paper / dx.doi.org/10.13182/NSE97-A24250
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 19-23
Technical Paper / dx.doi.org/10.13182/NSE97-A24251
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 24-50
Technical Paper / dx.doi.org/10.13182/NSE97-A24252
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 51-60
Technical Paper / dx.doi.org/10.13182/NSE97-A24253
Study of Total Discrete Gamma Radiation from Aluminum Under 14.9-MeV Neutron Bombardment
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 61-74
Technical Paper / dx.doi.org/10.13182/NSE97-A24254
The Role of Heater Thermal Response in Reactor Thermal Limits During Oscillatory Two-Phase Flows
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 75-83
Technical Paper / dx.doi.org/10.13182/NSE97-A24255
An Estimation of the Energy Generation Potential of Proton-Driven Subcritical ThO2 Lattices
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 84-92
Technical Paper / dx.doi.org/10.13182/NSE97-A24256
Sensitivity Study of the Positive Scram Effect Relevant to the Chernobyl Accident Simulation
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 93-100
Technical Paper / dx.doi.org/10.13182/NSE97-A24257
A New Variational Functional for Space-Time Neutronics
Nuclear Science and Engineering / Volume 125 / Number 1 / January 1997 / Pages 101-106
Technical Note / dx.doi.org/10.13182/NSE97-A24258
Response Functions for Neutron Skyshine Analysis
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 111-127
Technical Paper / dx.doi.org/10.13182/NSE97-A24261
A New Weight-Dependent Direct Statistical Approach Model
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 128-170
Technical Paper / dx.doi.org/10.13182/NSE97-A24262
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 171-177
Technical Paper / dx.doi.org/10.13182/NSE97-A24263
Resonance Calculations Using the Multiband Method and Interface Currents
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 178-187
Technical Paper / dx.doi.org/10.13182/NSE97-A24264
A Geometry-Independent Fine-Mesh-Based Monte Carlo Importance Generator
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 188-195
Technical Paper / dx.doi.org/10.13182/NSE97-A24265
Study of Gamma Radiation from the Interaction of 14.6-MeV Neutrons with 27Al
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 196-204
Technical Paper / dx.doi.org/10.13182/NSE97-A24266
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 205-217
Technical Paper / dx.doi.org/10.13182/NSE97-A24267
Positron-Emitting Radionuclide Yield in Deuterium Beam-Injected 3He Plasma
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 218-222
Technical Paper / dx.doi.org/10.13182/NSE97-A24268
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 223-231
Technical Paper / dx.doi.org/10.13182/NSE97-A24269
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 232-242
Technical Paper / dx.doi.org/10.13182/NSE97-A24270
Validation of Neutron Fluence Calculation Methodology for VVER-440 Vessel
Nuclear Science and Engineering / Volume 125 / Number 2 / February 1997 / Pages 243-247
Technical Paper / dx.doi.org/10.13182/NSE97-A24271
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 249-256
Technical Paper / dx.doi.org/10.13182/NSE97-A24273
A Transport Synthetic Acceleration Method for Transport Iterations
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 257-283
Technical Paper / dx.doi.org/10.13182/NSE97-A24274
Error Analysis of the Nodal Expansion Method for Solving the Neutron Diffusion Equation
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 284-299
Technical Paper / dx.doi.org/10.13182/NSE97-A24275
Parallel Processing of Two-Dimensional Sn Transport Calculations
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 300-313
Technical Paper / dx.doi.org/10.13182/NSE97-A24276
Generalized Rayleigh Quotients for Eigenvalue Estimates of Neutron Balance Equations
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 314-323
Technical Paper / dx.doi.org/10.13182/NSE97-A24277
Hierarchical Control of Reactor Inlet Temperature in Pool-Type Plants —I: Physics of Control
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 324-336
Technical Paper / dx.doi.org/10.13182/NSE97-A24278
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 337-347
Technical Paper / dx.doi.org/10.13182/NSE97-A24279
Numerical Simulation of Flow Behaviors in the Loop Seal Using First-Principle Equations
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 348-361
Technical Paper / dx.doi.org/10.13182/NSE97-A24280
Thermal Breeding of Tritium: A Comparative Study of the Li + C and 3He + C Systems
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 362-370
Technical Paper / dx.doi.org/10.13182/NSE97-A24281
Systematics of Isomeric Cross-Section Ratios for (n,2n), (n , p), (n, α) Reactions at 14.5 MeV
Nuclear Science and Engineering / Volume 125 / Number 3 / March 1997 / Pages 371-375
Technical Paper / dx.doi.org/10.13182/NSE97-A24282