Volume 54
Number 1 | Number 2 | Number 3 | Number 4
Number 1
Temperature Dynamic Analysis of Fuel Elements for Boiling Water Reactors
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 1-9
Technical Paper / dx.doi.org/10.13182/NSE74-A23387
Some Aspects of Fuel-Pin-Failure Propagation in Sodium-Cooled Fast Reactors
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 10-17
Technical Paper / dx.doi.org/10.13182/NSE74-A23388
The Thermal-Neutron Scattering Cross Sections of Uranium-233 and Thorium-232
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 18-27
Technical Paper / dx.doi.org/10.13182/NSE74-A23389
Age of Californium-252 Fission Neutrons to Indium Resonance Energy in Water
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 28-34
Technical Paper / dx.doi.org/10.13182/NSE74-A23390
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 35-46
Technical Paper / dx.doi.org/10.13182/NSE74-A23391
Simulation Studies of a Practical Reactor Control System Providing Time-Optimal Shutdown
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 47-54
Technical Paper / dx.doi.org/10.13182/NSE74-A23392
An Examination of Some Approximations for Heterogeneous Reactors
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 55-71
Technical Paper / dx.doi.org/10.13182/NSE74-A23393
Effects of Highly Anisotropic Scattering on Monoenergetic Neutron Transport at Deep Penetrations
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 72-84
Technical Paper / dx.doi.org/10.13182/NSE74-A23394
Legendre Polynomial Expansion of the Klein-Nishina Differential Cross Section
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 85-93
Technical Paper / dx.doi.org/10.13182/NSE74-A23395
Benchmark Values for the Slab and Sphere Criticality Problem in One-Group Neutron Transport Theory
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 94-99
Technical Note / dx.doi.org/10.13182/NSE54-94
Number 2
Relativistic Compton Scattering by the Discrete Ordinates Method
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 101-115
Technical Paper / dx.doi.org/10.13182/NSE74-A23399
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 116-126
Technical Paper / dx.doi.org/10.13182/NSE74-A23400
Neutron Pulses Slowing Down in Heavy Media Analysis with Applications of the Lead Spectrometer
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 127-142
Technical Paper / dx.doi.org/10.13182/NSE74-A23401
Correcting for Emission-Time Effects in Neutron Time-of-Flight Data Using Multiple Time Spectra
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 143-156
Technical Paper / dx.doi.org/10.13182/NSE74-A23402
Estimation of Reactivity Worths by Local Calculation
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 157-165
Technical Paper / dx.doi.org/10.13182/NSE74-A23403
Minimal Time Control of Spatial Xenon Oscillations in Nuclear Power Reactors
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 166-176
Technical Paper / dx.doi.org/10.13182/NSE74-A23404
Calculation of the Decay Power of Fission Products
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 177-189
Technical Paper / dx.doi.org/10.13182/NSE74-A23405
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 190-191
Technical Note / dx.doi.org/10.13182/NSE74-A23406
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 191-196
Technical Note / dx.doi.org/10.13182/NSE74-A23407
Functionals to Represent the Neutron Flux in Fast Pulsed Assemblies
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 196-200
Technical Note / dx.doi.org/10.13182/NSE74-A23408
Flux Synthesis Calculations for Fast Reactors
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 201-206
Technical Note / dx.doi.org/10.13182/NSE74-A23409
Application of an Improved Time-Difference Method for Spatial Xenon Transient Analysis
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 206-214
Technical Note / dx.doi.org/10.13182/NSE74-A23410
Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 214-232
Technical Note / dx.doi.org/10.13182/NSE74-A23411
Number 3
Prediction of Gamma-Ray Spectra at Deep Penetration Utilizing the Equilibrium Angular Distribution
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 235-253
Technical Paper / dx.doi.org/10.13182/NSE74-A23415
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 254-262
Technical Paper / dx.doi.org/10.13182/NSE74-A23416
The Yield of Short-Lived Gamma-Ray Emitting Nuclides from Fast- and Thermal-Neutron Fission
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 263-272
Technical Paper / dx.doi.org/10.13182/NSE74-A23417
Cobalt Fast-Neutron Cross Sections
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 273-285
Technical Paper / dx.doi.org/10.13182/NSE74-A23418
Neutron Cross Sections of Samarium-147 and Samarium-150
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 286-299
Technical Paper / dx.doi.org/10.13182/NSE74-A23419
Evaluation of Uranium-238 Neutron Cross Sections from Spectral Measurements
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 300-316
Technical Paper / dx.doi.org/10.13182/NSE74-A23420
The Ratio of the Uranium-233 to Uranium-235 Fission Cross Section
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 317-321
Technical Paper / dx.doi.org/10.13182/NSE74-1
Total Neutron Cross Sections of Uranium-235, Uranium-238, and Plutonium-239 from 0.5 to 15 MeV
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 322-326
Technical Paper / dx.doi.org/10.13182/NSE74-A23422
Anisotropic Neutron Diffusion in Lattices of the Zero-Power Plutonium Reactor Experiments
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 327-340
Technical Paper / dx.doi.org/10.13182/NSE74-A23423
A Theory for Pulsed-Neutron Experiments in Reactor Lattices
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 341-352
Technical Paper / dx.doi.org/10.13182/NSE74-A23424
A Solution of the Milne Problem Using Full-Range Completeness of Case’s Eigenfunctions
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 353-356
Technical Paper / dx.doi.org/10.13182/NSE74-A23425
Axial Neutron Streaming in Gas-Cooled Fast Reactors
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 357-360
Technical Note / dx.doi.org/10.13182/NSE74-A23426
The Effect of Position on the Criticality of Uranium Spheres in Uranium Solution Cylinders
Nuclear Science and Engineering / Volume 54 / Number 3 / July 1974 / Pages 360-366
Technical Note / dx.doi.org/10.13182/NSE74-A23427
Number 4
Generalized Collision Probabilities and Neutron Transport Eigenvalue Problems
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 369-375
Technical Paper / dx.doi.org/10.13182/NSE74-A23431
Weighted Central Difference Equations for the Neutron Transport Equation
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 376-386
Technical Paper / dx.doi.org/10.13182/NSE74-A23432
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 387-394
Technical Paper / dx.doi.org/10.13182/NSE74-A23433
Neutron and Gamma-Ray Effects on Self-Powered In-Core Radiation Detectors
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 395-415
Technical Paper / dx.doi.org/10.13182/NSE74-A23434
Small-Angle Scattering of 7.4- to 9.5-MeV Neutrons from Nitrogen and Oxygen
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 416-422
Technical Paper / dx.doi.org/10.13182/NSE74-A23435
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 423-431
Technical Paper / dx.doi.org/10.13182/NSE74-A23436
Accurate Kinetics Equations of a Square Cascade for Gas Separation
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 432-444
Technical Paper / dx.doi.org/10.13182/NSE74-A23437
Turbulence Measurements in a Magneto-Fluid-Mechanic Channel
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 445-449
Technical Paper / dx.doi.org/10.13182/NSE74-A23438
Partial-Range Analysis of the One-Speed Neutron Transport Equation with Anisotropic Scattering
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 450-455
Technical Note / dx.doi.org/10.13182/NSE74-A23439
An Asymptotic Solution in the Theory of Neutron Moderation
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 455-456
Technical Note / dx.doi.org/10.13182/NSE74-A23440
Application of the Finite Element Method to Two-Dimensional Diffusion Problems
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 456-465
Technical Note / dx.doi.org/10.13182/NSE74-A23441
A Rapid Calculational Method for Multigroup Elastic Transfer
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 465-467
Technical Note / dx.doi.org/10.13182/NSE74-A23442
On the Estimation of Errors in Reactor Theory
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 467-470
Technical Note / dx.doi.org/10.13182/NSE74-A23443
Neutron Yields from Uranium Isotopes in Uranium Hexafluoride
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 470-474
Technical Note / dx.doi.org/10.13182/NSE54-470
Optimization of Control-Rod Programming in Multiregion Nuclear Reactors
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 474-481
Technical Note / dx.doi.org/10.13182/NSE74-A23445
On the Mechanisms for Vapor Explosions
Nuclear Science and Engineering / Volume 54 / Number 4 / August 1974 / Pages 481-482
Technical Note / dx.doi.org/10.13182/NSE74-A23446
