ANS / Publications / Journals / Nuclear Science and Engineering

An Experimental Study of the Molten Glass/Water Thermal Interaction Under Free and Forced Conditions

V. H. Arakeri, I. Catton, and W. E. Kastenberg

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 153-166

Technical Paper / dx.doi.org/10.13182/NSE78-A27197

Fissile Fuel Doubling Time Characteristics for Reactor Lifetime Fuel Logistics

M. Heindler and A. A. Harms

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 167-187

Technical Paper / dx.doi.org/10.13182/NSE78-A27198

Cross Sections for the ¹¹B(α, p)¹⁴C Reaction in the Alpha-Particle Energy Range from 4.4 to 6.7 MeV

Wen-Sou Hou, Chia-Shou Lin, Ming Wen, Hsiao-Hua Hsu, and Jen-Chang Chou

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 188-192

Technical Paper / dx.doi.org/10.13182/NSE78-A27199

Spectral Fine-Structure Effects in the Reactivity-Reaction-Rate Method for Determining Capture-to-Fission Ratios

E. Greenspan, Y. Karni

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 193-204

Technical Paper / dx.doi.org/10.13182/NSE78-A27200

Measurement of the Fission Cross Sections of Uranium-233 and Plutonium-239 Relative to Uranium-235 from 1 keV to 30 MeV

G. W. Carlson and J. W. Behrens

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 205-216

Technical Paper / dx.doi.org/10.13182/NSE78-1

Neutron Capture Probabilities for Thick Samples at Resonance Energies

Makio Ohkubo

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 217-228

Technical Paper / dx.doi.org/10.13182/NSE78-A27202

The Importance Factor of a Source in Reactor Kinetics

J. Ligou

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 229-234

Technical Paper / dx.doi.org/10.13182/NSE78-A27203

Polynomial Approach to Reactor Kinetics Equations

Kueng Yeh

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 235-242

Technical Paper / dx.doi.org/10.13182/NSE78-A27204

Cross-Section Sensitivity Analysis of ²³⁵U and ²³⁸U Fission Rates Measured in a Graphite-Reflected Lithium Assembly

Yasushi Seki and Hiroshi Maekawa

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 243-251

Technical Note / dx.doi.org/10.13182/NSE78-A27205

Extension of the Width Fluctuation Correction to Reactions Involving Continuum Level Excitations

G. Reffo and F. Fabbri

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 251-254

Technical Note / dx.doi.org/10.13182/NSE78-A27206

On Approximations to the Neutron Escape Probability from an Absorbing Body

Yung-An Chao, Aquilino Senra Martinez

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 254-258

Technical Note / dx.doi.org/10.13182/NSE66-254

Remark on the Efficiency of Track-Length Estimators in Reaction Rate Estimations

I. Lux

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 258-264

Technical Note / dx.doi.org/10.13182/NSE78-A27208

Determination of Void Fraction Profile in a Boiling Water Reactor Channel Using Neutron Noise Analysis

M. Ashraf Atta, D. N. Fry, J. E. Mott, and W. T. King

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 264-268

Technical Note / dx.doi.org/10.13182/NSE78-A27209