American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 36 / Number 3

Volume 36

Number 3

Calculation of Temperature Distributions in Fuel Rods with Varying Conductivity and Asymmetric Flux Distribution

D. G. Andrews, M. Dixmier

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

M. H. Fontana, R. E. Bailey

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

John C. Hopkins, D. M. Drake

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

J. K. Dickens, F. G. Perey

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 280-290

Technical Paper / dx.doi.org/10.13182/NSE69-A18725

Calculation of the Neutron and Proton Spectra from Thick Targets Bombarded by 450-MeV Protons and Comparison with Experiment

R. G. Alsmiller, Jr., J. W. Wachter, H. S. Moran

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

Ricardo Artigas, H. E. Hungerford

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

R. D. Shelton, H. E. Stern, J. W. Watts

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

G. Bitelli, M. Salvatores

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

B. Fredin, T. Boševski, M. Mataušek

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 315-325

Technical Paper / dx.doi.org/10.13182/NSE69-A18730

Neutron Diffusion in Aluminum-Water Lattices: Measurements of Anisotropy in the Continuous Eigenvalue Region

Philip F. Palmedo, John F. Conant

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 326-335

Technical Paper / dx.doi.org/10.13182/NSE69-A18731

A Detailed Method for Calculating the Low Energy Multigroup Cross Sections and the Doppler Coefficient in a Fast Reactor

C. R. Adkins, T. E. Murley, M. W. Dyos

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

A. Rastas, J. Saastamoinen

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

W. Ciechanowicz, K. O. Solberg

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

Wataru Shinoda, Susumu Mitake

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

Weston M. Stacey, Jr.

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

K. O. Ott, D. A. Meneley

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 402-411

Technical Paper / dx.doi.org/10.13182/NSE36-402

Analytical and Experimental Investigations of the Kinetic Behavior of a Uranium-Dioxide-Fueled Pressurized-Water Reactor

J. E. Houghtaling, J. E. Grund

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

C. W. Garrard, Jr., R. S. Wick

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

Rainer Grumbach

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

W. W. Clendenin

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

William G. Davey

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 434-435

Technical Note / dx.doi.org/10.13182/NSE69-A18742

Space-Angle Synthesis

Harry S. Zwibel, Bradley Bowes

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

L. L. Carter, N. J. McCormick

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

V. Aiello, G. Maracci, F. Rustichelli

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

C. H. Adams, W. M. Stacey, Jr.

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

G. R. Bond, C. E. Siewert

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

H. Kschwendt

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

J. Mika, R. Stankiewicz

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

Paul Nelson, Jr.

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 453-455

Technical Note / dx.doi.org/10.13182/NSE69-A18750