Number 1
A Three-Dimensional Stochastic Gamma-Ray Transport Method for Shielding Calculations
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE71-A22330
Monte Carlo Calculation of the Effect of Subterranean Perturbations on Reflected X Rays
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 12-21
Technical Paper | doi.org/10.13182/NSE71-A22331
Integral Reaction Rate Determinations—Part I. Tailored Reactor Spectrum Preparation and Measurement
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 22-30
Technical Paper | doi.org/10.13182/NSE71-A22332
Integral Reaction Rate Determinations—Part II: Fission Rate Measurements
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 31-41
Technical Paper | doi.org/10.13182/NSE71-A22333
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 42-52
Technical Paper | doi.org/10.13182/NSE71-A22334
Spectra of Fast Neutrons from Water Pulsed with 14-MeV Neutrons
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 53-60
Technical Paper | doi.org/10.13182/NSE71-A22335
Neutron Flux in Cells of Finite, Square Lattices
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 61-75
Technical Paper | doi.org/10.13182/NSE71-A22336
Criticality Measurements on Uranium Metal Spheres Immersed in Uranium Solution
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 76-87
Technical Paper | doi.org/10.13182/NSE71-A22337
Optimal Control Rod Programming of Light Water Reactors in Equilibrium Fuel Cycle
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 88-111
Technical Paper | doi.org/10.13182/NSE71-A22338
Application of Linear Programming to Refueling Optimization for Light Water Moderated Power Reactors
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 112-130
Technical Paper | doi.org/10.13182/NSE71-A22339
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 131-139
Technical Paper | doi.org/10.13182/NSE71-A22340
Optimal Strategies in Reactor System Economics
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 140-147
Technical Note | doi.org/10.13182/NSE71-A22341
New Method for Measurement of the Effective Fraction of Delayed Neutrons from Fission
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 147-148
Technical Note | doi.org/10.13182/NSE71-A22342
Measurements of the Total Neutron Cross Section of Praseodymium Between 1 and 18 MeV
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 148-150
Technical Note | doi.org/10.13182/NSE71-A22343
Synthesis of Fast Reactor Neutron Energy Spectra
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 150-159
Technical Note | doi.org/10.13182/NSE71-A22344
Number 2
Regional-Dependent Reactor Kinetics
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 169-178
Technical Paper | doi.org/10.13182/NSE71-A22351
Noise and Transient Kinetics Experiments and Calculations for Loosely Coupled Cores
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 179-196
Technical Paper | doi.org/10.13182/NSE71-A22352
Optimum Bounds for Space-Time Reactor Problems Using Linear Programming
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 197-202
Technical Paper | doi.org/10.13182/NSE71-A22353
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 203-213
Technical Paper | doi.org/10.13182/NSE71-A22354
Pulsed-Neutron Diffusion Parameters in Mixtures of Heavy and Light Water and Ice
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 214-222
Technical Paper | doi.org/10.13182/NSE71-A22355
The Temperature Dependence of Neutron Inelastic Scattering from Water
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 223-235
Technical Paper | doi.org/10.13182/NSE71-A22356
Measured Neutron Spectra in a Number of Uranium- and Plutonium-Fueled Reactor Assemblies
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 236-243
Technical Paper | doi.org/10.13182/NSE71-A22357
Measurements of Thermal-Neutron Spectra in Plutonium Nitrate Solutions
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 244-254
Technical Paper | doi.org/10.13182/NSE71-A22358
Statistical Model Calculations of Iron-56 Neutron Cross Sections
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 255-265
Technical Paper | doi.org/10.13182/NSE71-A22359
Parametric Fit of the Neutron Cross Section of Holmium
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 266-273
Technical Paper | doi.org/10.13182/NSE71-A22360
Application of Linear Programming to In-Core Fuel Management Optimization in Light Water Reactors
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 274-283
Technical Paper | doi.org/10.13182/NSE71-A22361
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 284-303
Technical Paper | doi.org/10.13182/NSE71-A22362
Advances in the Generalized Perturbation Theory
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 304-309
Technical Note | doi.org/10.13182/NSE46-304
New Difference Schemes for the Neutron Transport Equation
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 309-314
Technical Note | doi.org/10.13182/NSE46-309
Neutron Absorption Cross Sections for Zirconium-94 and Zirconium-96
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 314-317
Technical Note | doi.org/10.13182/NSE71-A22365
Positive Difference Schemes in Neutron Spectral Codes
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 317-320
Technical Note | doi.org/10.13182/NSE71-A22366
Number 3
- Table of Contents
- MECC-3, A Monte Carlo Intranuclear-Cascade Code for Medium-Energy (<3500 MeV) Particle-Nucleus Collisions
- VIXEN
- Dynamics of Nuclear Reactors
- Monte Carlo Principles and Neutron Transport Problems
- Nuclear Theory, Volume 1: Nuclear Models
- Radiation Heat Transfer
- Nuclear Heal Transport
- New Method for Measurement of the Effective Fraction of Delayed Neutrons from Fission
Plasma Energy Deposition from Nuclear Elastic Scattering
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 323-333
Technical Paper | doi.org/10.13182/NSE71-A22370
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 334-355
Technical Paper | doi.org/10.13182/NSE71-A22371
Fast Neutron Total and Scattering Cross Sections of Uranium-238
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 356-365
Technical Paper | doi.org/10.13182/NSE71-A22372
A New Solution of the Point Kinetics Equations
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 366-375
Technical Paper | doi.org/10.13182/NSE71-A22373
Evaluation of Neutron Spectral Effects in a Plutonium-Fueled Lattice by Foil Activation
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 376-384
Technical Paper | doi.org/10.13182/NSE71-A22374
Application of Nonlinear Programming to the Optimal Control of Point Model Nuclear Reactors
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 385-393
Technical Paper | doi.org/10.13182/NSE71-A22375
Heated Laminar Gas Flow in Annuli with Temperature-Dependent Transport Properties
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 394-407
Technical Paper | doi.org/10.13182/NSE71-A22376
Dynamic Effects in Radiation Diagnosis of Fluctuating Voids
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 408-413
Technical Paper | doi.org/10.13182/NSE71-A22377
Fission Temperatures as a Function of the Average Number of Neutrons from Fission
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 414-416
Technical Note | doi.org/10.13182/NSE71-A22378
Neutron Diffusion from a Fast Point Source in Aqueous Absorbing Solutions
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 416-421
Technical Note | doi.org/10.13182/NSE71-A22379
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 421-425
Technical Note | doi.org/10.13182/NSE71-A22380
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 425-427
Technical Note | doi.org/10.13182/NSE71-A22381
Calculated Thermal (n, α) Cross Section for Nickel-59
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 427-428
Technical Note | doi.org/10.13182/NSE71-A22382
On a Possible Resolution of the Nitrogen Nonelastic Neutron Cross-Section Discrepancy Below 9 MeV
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 428-431
Technical Note | doi.org/10.13182/NSE71-A22383
Critical Heat Fluxes of Full Flux Shapes from Partial Flux Shapes
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 431-436
Technical Note | doi.org/10.13182/NSE71-A22384