Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 259-267
Technical Paper / dx.doi.org/10.13182/NSE69-A18722
The Computation of the Equilibrium Vapor Composition Over UO2 + x
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 268-274
Technical Paper / dx.doi.org/10.13182/NSE69-A18723
Elastic and Inelastic Scattering of Fast Neutrons from 10B, 11B, Natural Ge, and 93NB
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 275-279
Technical Paper / dx.doi.org/10.13182/NSE69-A18724
The 14N(n, xγ) Reaction for 5.8 ≤ En ≤ 8.6 MeV
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 280-290
Technical Paper / dx.doi.org/10.13182/NSE69-A18725
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 291-294
Technical Paper / dx.doi.org/10.13182/NSE69-A18726
A Numerical Treatment of the Attenuation of Neutrons by Air Ducts in Shields
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 295-303
Technical Paper / dx.doi.org/10.13182/NSE69-A18727
Advantages of Using a Combination Electromagnetic and Material Shield
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 304-308
Technical Paper / dx.doi.org/10.13182/NSE69-A18728
Neutron Flux and Importance Distribution by Collision Method, Starting from a Generalized Source
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 309-314
Technical Paper / dx.doi.org/10.13182/NSE69-A18729
Discrete Energy Representation of Thermal-Neutron Spectra in Uranium-Plutonium Lattices
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 315-325
Technical Paper / dx.doi.org/10.13182/NSE69-A18730
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 326-335
Technical Paper / dx.doi.org/10.13182/NSE69-A18731
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 336-350
Technical Paper / dx.doi.org/10.13182/NSE69-A18732
Neutron Rethermalization Near a Temperature Discontinuity Between Terphenyl and Light Water
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 351-360
Technical Paper / dx.doi.org/10.13182/NSE69-A18733
On Transient Digital Control of a Linear Model of the Halden Boiling Water Reactor
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 361-371
Technical Paper / dx.doi.org/10.13182/NSE69-A18734
A Three-Dimensional Analysis of Xenon-Induced Oscillations in Boiling Water Cooled Reactors
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 372-388
Technical Paper / dx.doi.org/10.13182/NSE69-A18735
Stochastic Kinetic Theory for a Space- and Energy-Dependent Zero Power Nuclear Reactor Model
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 389-401
Technical Paper / dx.doi.org/10.13182/NSE69-A18736
Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 402-411
Technical Paper / dx.doi.org/10.13182/NSE36-402
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 412-426
Technical Paper / dx.doi.org/10.13182/NSE69-A18738
Pressure Pulse Propagation in an Annular Flowing Two-Phase System
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 427-429
Technical Note / dx.doi.org/10.13182/NSE69-A18739
A Systematic Comparison of Different Hydrodynamics Models
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 429-433
Technical Note / dx.doi.org/10.13182/NSE69-A18740
Monatomic Gas Cross Section Expansion Coefficients
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 433-434
Technical Note / dx.doi.org/10.13182/NSE69-A18741
Selected Fission Cross Sections for 236U
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 434-435
Technical Note / dx.doi.org/10.13182/NSE69-A18742
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 435-438
Technical Note / dx.doi.org/10.13182/NSE69-A18743
Source Convergence in Monte Carlo Calculations
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 438-441
Technical Note / dx.doi.org/10.13182/NSE69-1
Single Rod Fine Distribution of the Fast Fission Ratio
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 441-444
Technical Note / dx.doi.org/10.13182/NSE69-A18745
An Anomaly Arising in the Collapsed-Group Flux Synthesis Approximation
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 444-447
Technical Note / dx.doi.org/10.13182/NSE69-A18746
On the Milne-Problem Extrapolation Distance
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Page 447
Technical Note / dx.doi.org/10.13182/NSE69-A18747
Application of the jN Method to Neutron Transport in Slabs and Spheres
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 447-450
Technical Note / dx.doi.org/10.13182/NSE69-A18748
Equivalence of Integral Transform and Spatial Spherical Harmonics Methods
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 450-453
Technical Note / dx.doi.org/10.13182/NSE69-A18749
Collisional Importance and Adjoint Problems in Neutron Transport
Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 453-455
Technical Note / dx.doi.org/10.13182/NSE69-A18750