Volume 55

Number 2

Table of Contents
Calculation of Temperature Distributions in Fuel Rods with Varying Conductivity and Asymmetric Flux Distribution(D. G. Andrews, M. Dixmier, D. G. Andrews, M. Dixmier)
An Asymptotic Solution in the Theory of Neutron Moderation(C. E. Siewert and A. R. Burkart, C. E. Siewert, A. R. Burkart)
Comments on “A Method of Computing Fission-Product Decay Heat in a Reactor with Time-Dependent Flux”(K. Shure)

Space-Time Nuclear Reactor Analysis by Temporal Transformation

W. J. Garland, A. A. Harms, J. Vlachopoulos

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 119-128

Technical Paper / dx.doi.org/10.13182/NSE74-A28202

Measurements at the Critical Facility for the In-Core Thermionic Reactor and Comparison with Calculations

M. Bloser, N. Kirch, F. J. Krings, A. Naseband, N. Paul

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 129-146

Technical Paper / dx.doi.org/10.13182/NSE74-A28203

Radiation-Transport Cross-Section Sensitivity Analysis— A General Approach Illustrated for a Thermonuclear Source in Air

D. E. Bartine, E. M. Oblow, F. R. Mynatt

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 147-167

Technical Paper / dx.doi.org/10.13182/NSE74-A28204

Gamma-Ray-Production Cross Sections for the ⁵⁶Fe(n,n’y) Reaction from 2.5- to 14.1-MeV Neutron Energies

J. Lachkar, J. Sigaud, Y. Patin, G. Haouat

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 168-187

Technical Paper / dx.doi.org/10.13182/NSE74-A28205

Prompt-Neutron Yield from the Spontaneous Fission of Californium-252

J. W. Boldeman

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 188-202

Technical Paper / dx.doi.org/10.13182/NSE74-A28206

Measurement of the Fission Cross Section of Uranium-235 for Incident Neutrons with Energies Between 2 and 100 keV

R. B. Perez, G. de Saussure, E. G. Silver, R. W. Ingle, H. Weaver

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 203-218

Technical Paper / dx.doi.org/10.13182/NSE74-A28207

Optimum Active-Inactive Times in Supervised Protective Systems for Nuclear Reactors

J. M. Kontoleon, Nadia Kontoleon, N. G. Chrysochoides

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 219-224

Technical Paper / dx.doi.org/10.13182/NSE74-A28208

Transport Calculations of the Neutron Escape Probability

A. M. Melandri, F. Premuda, G. P. Prelati

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 225-233

Technical Note / dx.doi.org/10.13182/NSE74-A28209

Half-Range Orthogonality Theorem for Thermal-Neutron Transport

Yuji Ishiguro

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 233-234

Technical Note / dx.doi.org/10.13182/NSE74-A28210

On the Randomness of a Neutron’s Kinetic Energy as It Slows Down by Elastic Collisions in an Infinite Medium

C. S. Barnett

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 234-242

Technical Note / dx.doi.org/10.13182/NSE74-A28211

Incomplete Neutron Thermalization in Light Water Ice at 77, 21, and 4 K

G. S. Gangwani, L. S. Kothari

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 242-243

Technical Note / dx.doi.org/10.13182/NSE74-A28212

Cross Sections of Aluminum and Iron Averaged Over the Californium-252 Fission Neutron Spectrum

W. G. Alberts, M. Matzke

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 243-244

Technical Note / dx.doi.org/10.13182/NSE74-A28213

Reexamination of the Value for the Minimum Critical Concentration of Plutonuim -239 in Water

C. R. Richey

Nuclear Science and Engineering / Volume 55 / Number 2 / October 1974 / Pages 244-247

Technical Note / dx.doi.org/10.13182/NSE74-A28214