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Volume 62 / Number 4

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Nuclear Science and Engineering / Volume 62 / Number 4

April 1977

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

P. Cloth, H. Conrads

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

April 1977

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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 / Pages 601-616

April 1977

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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 / Pages 617-626

April 1977

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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 / Pages 627-635

April 1977

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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 / Pages 636-651

April 1977

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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 / Pages 652-659

April 1977

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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 / Pages 660-694

April 1977

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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 / Pages 695-708

April 1977

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An Improved Response Matrix Method for Calculating Neutron Flux Distributions

Toshikazu Takeda, Kazuo Azekura, Tadahiro Ohnishi

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

April 1977

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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 / Pages 716-725

April 1977

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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 / Pages 726-735

April 1977

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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 / Pages 736-738

April 1977

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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 / Pages 738-743

April 1977

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Neutron Spectrum in a Heavy Gas

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

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

April 1977

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Neutron Diffusion in Finite Blocks of Beryllium

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

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

April 1977

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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 / Pages 751-756

April 1977

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Some Properties of the Width Fluctuation Factor

H. Gruppelaar, G. Reffo

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

April 1977

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Nuclear Reactor Control Using Walsh Function Variational Synthesis

S. Tzafestas, N. Chrysochoides

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

April 1977

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Nuclear Structure, Vol. II: Nuclear Deformations

L. W. Nordheim

Nuclear Science and Engineering / Volume 62 / Number 4 / Page 771

April 1977

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