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Volume 22

Number 1

Seven-Rod Bundle, Natural-Circulation, Stability and Burn-Out Tests with Water at up to 28 Atmospheres Pressure

R. W. Bowring, C. L. Spigt

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 1-13

Technical Paper / dx.doi.org/10.13182/NSE65-A19756

Purification of Beryllium by Acetylacetone — EDTA Solvent Extraction: Procedure and Chemistry

C. E. L. Bamberger, H. F. McDuffie, C. F. Baes, Jr.

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 14-19

Technical Paper / dx.doi.org/10.13182/NSE65-A19757

Measurements of the Epicadmium Capture-to-Fission Cross-Section Ratio in U235

D. E. Conway, H. D. Cook, S. B. Gunst

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 20-23

Technical Paper / dx.doi.org/10.13182/NSE65-A19758

Corrosion of Carbon Steel by Boiling and Superheated Mercury

A. H. Fleitman, A. J. Romano and C. J. Klamut

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 24-32

Technical Paper / dx.doi.org/10.13182/NSE65-A19759

Comparisons of Measured and Calculated Neutron Fluxes in Laminated Iron and Heavy Water

Erkki J. Aalto

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 33-39

Technical Paper / dx.doi.org/10.13182/NSE65-A19760

Neutron Thermalization Studies in Graphite

K. Serdula, J. Young

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 40-50

Technical Paper / dx.doi.org/10.13182/NSE65-A19761

Stable Numerical Solutions of the Reactor Kinetics Equations

K. F. Hansen, B. V. Koen, W. W. Little, Jr.,

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 51-59

Technical Paper / dx.doi.org/10.13182/NSE65-A19762

About the Generalization of Amouyal-Benoist's Method for Calculating Disadvantage Factors and Flux Distributions in Two-region Cells

Z. Weiss

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 60-77

Technical Paper / dx.doi.org/10.13182/NSE65-A19763

Improvements to the Theory of Resonance Escape in Heterogeneous Fuel: I. Regular Arrays of Fuel Rods

D. C. Leslie, J. G. Hill, A. Jonsson

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 78-86

Technical Paper / dx.doi.org/10.13182/NSE65-A19764

The Extrapolation Distance at the Surface of a Grey Cylindrical Control Rod

N. Spinks

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 87-93

Technical Paper / dx.doi.org/10.13182/NSE65-A19765

The Effects of Flux Anisotropy on Thermal-Neutron Flux Perturbations

J. V. Walker

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 94-101

Technical Paper / dx.doi.org/10.13182/NSE65-A19766

Measurement of Anisotropic Fast-Neutron Spectrum with Nuclear Emulsion

Tsutomu Iijima, Shoji Nomoto

Nuclear Science and Engineering / Volume 22 / Number 1 / May 1965 / Pages 102-110

Technical Paper / dx.doi.org/10.13182/NSE65-A19767