Volume 28
Number 1 | Number 2 | Number 3
Number 1
- Table of Contents
- Further Comment on the Optimal Shutdown Control
- Optimal Shutdown Control
- Comment on the Optimal Shutdown Control
- Comments on the Time Optimal Xenon Shutdown Problem
- Remarks With Regard to an Article by Tassan
- Answer to Mr. Stamm'ler's Comments on Article on Thermal Spectrum Measurements
- Thermal Cross Section and Resonance Integrals of Cadmium-114
- The Thermal-Neutron Milne Problem with a Two-Term Degenerate Kernel
Use of Hydraulic Models in Nuclear Reactor Design
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 1-11
Technical Paper / dx.doi.org/10.13182/NSE67-A18661
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 12-19
Technical Paper / dx.doi.org/10.13182/NSE67-A18662
The Use of Spherical UO2 in a Cermet Fuel Plate
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 20-33
Technical Paper / dx.doi.org/10.13182/NSE67-A18663
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 34-41
Technical Paper / dx.doi.org/10.13182/NSE67-A18664
Irradiation Behavior of Uranium Fuel Tubes in a Pressurized Heavy-Water Reactor
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 42-50
Technical Paper / dx.doi.org/10.13182/NSE67-A18665
The Compatibility of Graphite with Cesium
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 51-54
Technical Paper / dx.doi.org/10.13182/NSE67-A18666
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 55-61
Technical Paper / dx.doi.org/10.13182/NSE67-A18667
Measurement of Fissions Produced in Bulk Plutonium-239 by 2-eV to 10-keV Neutrons
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 62-71
Technical Paper / dx.doi.org/10.13182/NSE67-A18668
Power Oscillations and the Describing Function in Reactors with Linear Feedback
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 72-81
Technical Paper / dx.doi.org/10.13182/NSE67-A18669
The Application of a Hybrid Computer to the Analysis of Transient Phenomena in a Fast Reactor Core
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 82-92
Technical Paper / dx.doi.org/10.13182/NSE67-A18670
Solution of Group-Diffusion Equation Using Green's Function
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 93-104
Technical Paper / dx.doi.org/10.13182/NSE67-A18671
An Analogy Between Time-Dependent Diffusion Theory and Classical Mechanics
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 105-110
Technical Paper / dx.doi.org/10.13182/NSE67-A18672
Inelastic Scattering Measurements in a Fast Reactor by the Spherical Shell Method
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 111-123
Technical Paper / dx.doi.org/10.13182/NSE67-A18673
Anisotropic Scattering Coefficients in the Constant Cross-Section Transport Equation
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 124-126
Technical Paper / dx.doi.org/10.13182/NSE67-A18674
The Effect of Anisotripic Scattering in Plane-Geometry Transport Theory and Monte Carlo Calculations
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 127-132
Technical Paper / dx.doi.org/10.13182/NSE67-A18675
Total Neutron Cross Section of Protactinium-233
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 133-138
Technical Paper / dx.doi.org/10.13182/NSE67-A18676
The Thermal-Neutron Capture Cross Section of 147Sm
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 139-143
Technical Paper / dx.doi.org/10.13182/NSE67-A18677
Dose Buildup Factors of Plane Parallel Barriers For 137Cs Plane Monodirectional Source
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 144-145
Technical Note / dx.doi.org/10.13182/NSE67-A18678
Method for Calculating Average Thermal Neutron Parameters
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 145-148
Technical Note / dx.doi.org/10.13182/NSE67-A18679
Comment on the Calculation of the Scattering Cross Section for Multiple Resonances
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 149-150
Technical Note / dx.doi.org/10.13182/NSE67-A18680
A Limitation of the Roussopoulos Variational Principle?
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 150-152
Technical Note / dx.doi.org/10.13182/NSE67-A18681
Asymptotic Neutron Pulse Velocity and the System Dispersion Law
Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 152-154
Technical Note / dx.doi.org/10.13182/NSE67-A18682
Number 2
- Table of Contents
- Relativistic Theory of Reactions
- Introduction to Nuclear Reactor Theory
- Matrices and Linear Transformations
- Comments on “Stability Analysis of a Sampled-Data Controlled Nuclear Reactor System”
- Reply to T. J. Marciniak's Comments on “Stability Analysis of a Sampled-Data Controlled Nuclear Reactor System”
The Application of Lie Series to Reactor Theory
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 159-165
Technical Paper / dx.doi.org/10.13182/NSE67-A17465
Canonical and Involutory Transformations of the Variational Problems of Transport Theory
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 166-176
Technical Paper / dx.doi.org/10.13182/NSE67-A17466
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 177-189
Technical Paper / dx.doi.org/10.13182/NSE67-A17467
A Two-Region Problem in Time-Dependent Monoenergetic Neutron Transport Theory. I. Analysis
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 190-197
Technical Paper / dx.doi.org/10.13182/NSE67-A17468
A Two-Region Problem in Time-Dependent Monoenergetic Neutron Transport Theory. II. Applications
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 198-202
Technical Paper / dx.doi.org/10.13182/NSE67-A17469
Solution of the Neutron Slowing Down Problem via a Multiple Collision Approach
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 203-214
Technical Paper / dx.doi.org/10.13182/NSE67-A17470
First-Flight Collision Probabilities in Pin Clusters and Rod Lattices
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 215-225
Technical Paper / dx.doi.org/10.13182/NSE67-A17471
Determination of Stability Domains in Point Reactor Dynamics
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 226-236
Technical Paper / dx.doi.org/10.13182/NSE67-A17472
Point-Reactor Theory of Rossi-Alpha Experiment
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 237-242
Technical Paper / dx.doi.org/10.13182/NSE67-A17473
Interval Distributions in Neutron Counting Statistics
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 243-246
Technical Paper / dx.doi.org/10.13182/NSE67-A17474
An Analysis of Neutron Thermalization in Beryllium
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 247-258
Technical Paper / dx.doi.org/10.13182/NSE67-A17475
Neutron Thermalization in Light Water
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 259-269
Technical Paper / dx.doi.org/10.13182/NSE67-A17476
Analysis of Critical Experiments with Organic-Moderated Assemblies
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 270-276
Technical Paper / dx.doi.org/10.13182/NSE67-A17477
A Method for Absolute Determination of 238U Capture Rates in Fast Zero-Power Reactors
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 277-285
Technical Paper / dx.doi.org/10.13182/NSE67-A17478
The Thermal-Neutron Capture Cross Section of Deuterium
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 286-292
Technical Paper / dx.doi.org/10.13182/NSE67-A17479
Total Cross Sections of Calcium and Potassium for Fast Neutrons
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 293-295
Technical Paper / dx.doi.org/10.13182/NSE67-A17480
Effective Hot-Channel Factors for “Flat” Power Reactors
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 296-300
Technical Paper / dx.doi.org/10.13182/NSE67-A17481
Liquid-Metal Heat Transfer in a Parallel-Plate Channel with Periodic Boundary Conditions
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 301-305
Technical Note / dx.doi.org/10.13182/NSE67-A17482
The Gamma-Ray Branching of Krypton-85
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 305-306
Technical Note / dx.doi.org/10.13182/NSE67-A17483
Some Measurements of Decay Constants Close to (v ∑inel)min in Pulsed BeO Assemblies
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 306-308
Technical Note / dx.doi.org/10.13182/NSE67-A17484
Computation of Time-Dependent Neutron Spectra in D2O
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 308-310
Technical Note / dx.doi.org/10.13182/NSE67-A17485
On the Boundary Condition on the Flux of Monoenergetic Neutrons at a Plane Black Boundary
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Page 310
Technical Note / dx.doi.org/10.13182/NSE67-A17486
An Extension of the Path-Length Formalism to Anisotropic Charged-Particle Sources
Nuclear Science and Engineering / Volume 28 / Number 2 / May 1967 / Pages 311-312
Technical Note / dx.doi.org/10.13182/NSE67-A17487
Number 3
Stability Considerations in Two-Phase Flow
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 317-324
Technical Paper / dx.doi.org/10.13182/NSE67-A28945
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 325-337
Technical Paper / dx.doi.org/10.13182/NSE67-A28946
Recovery of Beryllium from Acid Leaches of Beryl by Solvent Extraction
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 338-345
Technical Paper / dx.doi.org/10.13182/NSE67-A28947
Preparation of High-Purity Beryllium Compounds by Solvent Extraction
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 346-352
Technical Paper / dx.doi.org/10.13182/NSE67-A28948
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 353-358
Technical Paper / dx.doi.org/10.13182/NSE67-A28949
Parameters for the First Neutron Resonance in 113Cd
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 359-363
Technical Paper / dx.doi.org/10.13182/NSE67-A28950
Angle-Space Synthesis-an Approach to Transport Approximations
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 364-375
Technical Paper / dx.doi.org/10.13182/NSE67-A28951
Multitable Treatments of Anisotropic Scattering in SN Multigroup Transport Calculations
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 376-383
Technical Paper / dx.doi.org/10.13182/NSE67-2
Noise-Equivalent Source in Nuclear Reactors
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 384-396
Technical Paper / dx.doi.org/10.13182/NSE67-A28953
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 397-403
Technical Paper / dx.doi.org/10.13182/NSE67-A28954
On the Experimental Application of the Neutron-Wave Technique to Thermal-Neutron Systems
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 404-414
Technical Paper / dx.doi.org/10.13182/NSE67-A28955
An Approximate Theory for the Slowing Down of Neutrons in a Nonmultiplying Medium
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 415-425
Technical Paper / dx.doi.org/10.13182/NSE67-A28956
Synthesis of Three-Dimensional Flux Shapes Using Discontinuous Sets of Trial Functions
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 426-437
Technical Paper / dx.doi.org/10.13182/NSE67-A28957
A General Modal-Expansion Method for Obtaining Approximate Equations for Linear Systems
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 438-442
Technical Paper / dx.doi.org/10.13182/NSE67-A28958
Fast-Reactor Calculational Models
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 443-449
Technical Paper / dx.doi.org/10.13182/NSE67-A28959
The Influence of Chemical Binding on Milne Problem Neutron Leakage Spectra
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 450-452
Technical Note / dx.doi.org/10.13182/NSE67-A28960
On the Noise-Equivalent Source in Zero-Power Reactor
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 452-456
Technical Note / dx.doi.org/10.13182/NSE67-A28961
Properties of the Relaxation Lengths in PL, Double-PL, and Angle-Space Synthesis-Type Approximations
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 456-458
Technical Note / dx.doi.org/10.13182/NSE67-A28962
The Correlation of the Energy of Single-Neutron Resonances Determined by Time-of-Flight Methods
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 458-461
Technical Note / dx.doi.org/10.13182/NSE67-A28963
Note on the Half-Width of the Neutron Pulse of a Pulsed Reactor
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Page 461
Technical Note / dx.doi.org/10.13182/NSE67-A28964
Extrapolation Distance in Water for Small Geometry
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 461-462
Technical Note / dx.doi.org/10.13182/NSE67-A28965
A Summation Scheme for Certain Series in Neutron Thermalization
Nuclear Science and Engineering / Volume 28 / Number 3 / June 1967 / Pages 462-463
Technical Note / dx.doi.org/10.13182/NSE67-A28966
