Number 1
A Study of Liquid Mass Transport in Annular Air-Water Flow
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 2-12
Technical Paper | doi.org/10.13182/NSE84-A17440
Thermal Design Concepts for the Rotating Fluidized Bed Reactor
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 13-27
Technical Paper | doi.org/10.13182/NSE84-A17441
Covariances of Neutron Fluxes and Cross Sections in Group Structure Variation
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 28-33
Technical Paper | doi.org/10.13182/NSE84-A17442
Preequilibrium Emission of Protons from 93Nb(n,p) Reaction at 14 MeV
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 34-40
Technical Paper | doi.org/10.13182/NSE84-A17443
The 12C(n,α) Reaction and the Kerma Factor for Carbon at En = 14.1 MeV
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 41-47
Technical Paper | doi.org/10.13182/NSE84-A17444
Neutron Capture in s-Wave Resonances of Nickel-64
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 48-58
Technical Paper | doi.org/10.13182/NSE84-A17445
Track Length Estimation Applied to Point Detectors
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 59-71
Technical Paper | doi.org/10.13182/NSE84-A17446
Diffusion Coefficients for Fast Reactor Hexagonal Assemblies
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 72-80
Technical Note | doi.org/10.13182/NSE84-A17447
Sensitivity Coefficients for Leakage and Nonleakage Components of Sodium Void Worth
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 80-84
Technical Note | doi.org/10.13182/NSE84-A17448
Extrapolation Distance in the Cylindrical Milne Problem in One- and Two-Group Transport Theory
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 84-96
Technical Note | doi.org/10.13182/NSE84-A17449
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 96-102
Technical Note | doi.org/10.13182/NSE84-A17450
Number 2
Neutron Transport Calculations in Cylindrical Geometry
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 107-112
Technical Paper | doi.org/10.13182/NSE84-A17705
Monte Carlo Calculation and Analytical Approximation of Gamma-Ray Buildup Factors in Air
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 113-122
Technical Paper | doi.org/10.13182/NSE84-A17706
Evaluation of Neutron Skyshine from a Cyclotron
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 123-135
Technical Paper | doi.org/10.13182/NSE84-A17707
Estimation of Population Variance in Contributon Monte Carlo
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 136-151
Technical Paper | doi.org/10.13182/NSE84-A17708
Concept of Shielding Characteristics for Spent Fuel Shipping Casks
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 152-180
Technical Paper | doi.org/10.13182/NSE84-A17709
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 181-189
Technical Note | doi.org/10.13182/NSE84-A17710
A Deuteron Energy Loss Evaluation in a Solid Ti-T Target Used for the T(d,n)4He Reaction
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 189-194
Technical Note | doi.org/10.13182/NSE84-A17711
Number 3
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 204-232
Technical Paper | doi.org/10.13182/NSE84-A17779
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 233-251
Technical Paper | doi.org/10.13182/NSE84-A17780
Critical Experiments Using an Axially Heterogeneous Assembly and Their Analysis
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 252-261
Technical Paper | doi.org/10.13182/NSE84-A17781
Worths and Interactions of Simulated Fast Breeder Reactor Control Rods in ZEBRA and SNEAK Assemblies
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 262-282
Technical Paper | doi.org/10.13182/NSE84-A17782
An Experimental Study of Reactivity Changes and Flux Distortion in Simulated LMFBR Meltdown Cores
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 283-294
Technical Paper | doi.org/10.13182/NSE84-A17783
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 295-313
Technical Paper | doi.org/10.13182/NSE84-A17784
Recent Developments in the Small-Sample Reactivity Discrepancy
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 314-332
Technical Paper | doi.org/10.13182/NSE84-A17785
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 333-348
Technical Paper | doi.org/10.13182/NSE87-333
Number 4
- Table of Contents
- Introductory Nuclear Reactor Statics
- Before It's Too Late, A Scientist's Case for Nuclear Energy
- Comment on a Sensitivity Coefficient in Depletion Perturbation Theory
- Reply to “Comment on a Sensitivity Coefficient in Depletion Perturbation Theory”
- Analysis of Finite Difference Approximation in a Discrete Ordinates Transport Equation in One-Dimensional Plane Geometry
- Response Matrix of Symmetric Nodes
Analytical Models for Simulating Hydrogen Transport in Reactor Containment Atmospheres
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 349-360
Technical Paper | doi.org/10.13182/NSE84-A18504
Core-Management Analysis of the Fugen Heavy-Water-Moderated Plutonium-Uranium Mixed Oxide Reactor
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 361-380
Technical Paper | doi.org/10.13182/NSE84-A18505
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 381-404
Technical Paper | doi.org/10.13182/NSE84-A18506
Release of Fission Products from Irradiated Aluminide Fuel at High Temperatures
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 405-417
Technical Paper | doi.org/10.13182/NSE84-A18507
Evaluation of Delayed-Neutron Emission Probabilities
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 418-431
Technical Paper | doi.org/10.13182/NSE84-A18508
Analysis of Neutron Yields from High-Energy Proton Bombardment of Uranium Targets
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 432-443
Technical Paper | doi.org/10.13182/NSE84-A18509
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 444-453
Technical Paper | doi.org/10.13182/NSE84-A18510
Application of an Exact Model Matching Technique to Coupled-Core Nuclear Reactor Control
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 454-460
Technical Note | doi.org/10.13182/NSE84-A18511
Optimization of the Fuel Cell of a Spectral Shift Controlled Reactor
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 460-469
Technical Note | doi.org/10.13182/NSE84-A18512
Anisotropic Turbulent Flow in Rod Bundles
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 469-478
Technical Note | doi.org/10.13182/NSE84-A18513
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 478-489
Technical Note | doi.org/10.13182/NSE84-A18514
On Statistical Identification of Important Input Variables to Large Codes
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 490-495
Technical Note | doi.org/10.13182/NSE84-A18515