Home / Publications / Journals / Nuclear Science and Engineering / Volume 62 / Number 4

Volume 62

Number 4

Table of Contents
Nuclear Structure, Vol. II: Nuclear Deformations(L. W. Nordheim)
Of Acceptable Risk: Science and the Determination of Safety(Roy Reider)
Environmental Aspects of Nuclear Power(Bernard L. Cohen)
Random Processes in Nuclear Reactors(Joseph A. Thie)
A Rational Finite Element Basis(J. P. Hennart)
FLASH6(J. J. Beyer, W. D. Peterson, D. A. Prelewicz, G. W. Swartele)

Neutronics of a Dense-Plasma Focus— An Investigation of a Fusion Plasma

P. Cloth, H. Conrads

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 591-600

Technical Paper / dx.doi.org/10.13182/NSE77-A15203

The Influence of Design Variations on Controlled Thermonuclear Reactor Blanket Neutronic Performance Using Variational Techniques

Edward T. Cheng, Robert W. Conn

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 601-616

Technical Paper / dx.doi.org/10.13182/NSE77-A15204

Monte Carlo Shielding Calculations Using Event-Value Path-Length Biasing

J. S. Tang, T. J. Hoffman, P. N. Stevens

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 617-626

Technical Paper / dx.doi.org/10.13182/NSE77-A15205

Delayed Neutron Yield Calculations for the Neutron-Induced Fission of Uranium-235 as a Function of the Incident Neutron Energy

D. R. Alexander, M. S. Krick

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 627-635

Technical Paper / dx.doi.org/10.13182/NSE77-A15206

Measured Near-Equilibrium Delayed Neutron Spectra Produced by Fast-Neutron-Induced Fission of ²³²Th, ²³³U, ²³⁵U, ²³⁸U, and ²³⁹Pu

George W. Eccleston, Gene L. Woodruff

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 636-651

Technical Paper / dx.doi.org/10.13182/NSE77-A15207

Equilibrium Delayed Neutron Spectra from Fast Fission of Uranium-235, Uranium-238, and Plutonium-239

Albert E. Evans, M. S. Krick

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 652-659

Technical Paper / dx.doi.org/10.13182/NSE77-A15208

Evaluated Delayed Neutron Spectra and Their Importance in Reactor Calculations

D. Saphier, D. Ilberg, S. Shalev, S. Yiftah

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 660-694

Technical Paper / dx.doi.org/10.13182/NSE77-A15209

An Experimental Study of the Prompt Fission Neutron Spectrum Induced by 0.5-MeV Neutrons Incident on Uranium-235

P. I. Johansson, B. Holmqvist

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 695-708

Technical Paper / dx.doi.org/10.13182/NSE77-A15210

An Improved Response Matrix Method for Calculating Neutron Flux Distributions

Toshikazu Takeda, Kazuo Azekura, Tadahiro Ohnishi

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 709-715

Technical Paper / dx.doi.org/10.13182/NSE77-A15211

Gamma-Ray Production Cross Sections for Copper from 0.67 to 19.6 MeV

V. C. Rogers, D. R. Dixon, C. G. Hoot, D. Costello, V. J. Orphan

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 716-725

Technical Paper / dx.doi.org/10.13182/NSE77-A15212

Effect of Fixed and Soluble Neutron Absorbers on the Criticality of Uranium-Plutonium Systems

R. C. Lloyd, E. D. Clayton

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 726-735

Technical Paper / dx.doi.org/10.13182/NSE77-A15213

Taylor Coefficients for Eisenhauer-Simmons Gamma-Ray Buildup Factors in Ordinary Concrete

K. Shure, O. J. Wallace

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 736-738

Technical Note / dx.doi.org/10.13182/NSE77-A15214

A Low-Order Approximation for Highly Anisotropic Multigroup Transport Cross Sections

Wayne J. Mikols, J. Kenneth Shultis

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 738-743

Technical Note / dx.doi.org/10.13182/NSE77-A15215

Neutron Spectrum in a Heavy Gas

Raymond L. Murray, Reed S. C. Rogers, Saber Musazay

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 743-745

Technical Note / dx.doi.org/10.13182/NSE77-A15216

Neutron Diffusion in Finite Blocks of Beryllium

A. N. Verma, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 745-750

Technical Note / dx.doi.org/10.13182/NSE77-A15217

A Coarse-Mesh Method for Multidimensional, Mixed-Lattice Diffusion Calculations

H. L. Dodds, Jr., H. C. Honeck, D. E. Hostetler

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 751-756

Technical Note / dx.doi.org/10.13182/NSE77-A15218

Some Properties of the Width Fluctuation Factor

H. Gruppelaar, G. Reffo

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 756-763

Technical Note / dx.doi.org/10.13182/NSE77-A15219

Nuclear Reactor Control Using Walsh Function Variational Synthesis

S. Tzafestas, N. Chrysochoides

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 763-770

Technical Note / dx.doi.org/10.13182/NSE77-A15220