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Volume 58

Number 3

Table of Contents
Venture(D. R. Vondy, T. B. Fowler, G. W. Cunningham)
Neutron Transport Theory(R. A. Bonalumi)
Elements of Nuclear Reactor Engineering(Andrew Robeson)
Albedo-Adjusted Fast-Neutron Diffusion Coefficients in Reactor Reflectors(William B. Terney)
Annual Review of Nuclear Science(W. Bennett Lewis, Gordon C. Ball, H. C. Lee, I. S. Towner)

Estimation and Optimal Feedback Control Theory Applied to a Nuclear Boiling Water Reactor

B. Frogner, L. M. Grossman

Nuclear Science and Engineering / Volume 58 / Number 3 / November 1975 / Pages 265-277

Technical Paper / dx.doi.org/10.13182/NSE75-A26776

Evaluation of Neutron Inelastic Scattering Cross Sections of Uranium-233 from Neutron Spectrum Measurements in Fast Media

R. Paviotti Corcuera

Nuclear Science and Engineering / Volume 58 / Number 3 / November 1975 / Pages 278-290

Technical Paper / dx.doi.org/10.13182/NSE75-A26777

Neutron-Absorption Cross Sections of Some Radioactive Nuclides

Myron F. Elgart, Harmon L. Finston, Robert Rundberg, Evan T. Williams, Albert H. Bond, Jr., Emmanuel Yellin

Nuclear Science and Engineering / Volume 58 / Number 3 / November 1975 / Pages 291-297

Technical Paper / dx.doi.org/10.13182/NSE75-A26778

Gamma-Ray Production Cross Sections for Carbon and Nitrogen from Threshold to 20.7 MeV

V. C. Rogers, V. J. Orphan, C. G. Hoot, V. V. Verbinski

Nuclear Science and Engineering / Volume 58 / Number 3 / November 1975 / Pages 298-313

Technical Paper / dx.doi.org/10.13182/NSE75-A26779

Cross-Section Measurement of (n, p) Reactions for ²⁷Al, ^46,47,48Ti, ^54,56Fe, ⁵⁸Ni, ⁵⁹Co, and ⁶⁴Zn from Near Threshold to 10 MeV

Donald L. Smith, James W. Meadows

Nuclear Science and Engineering / Volume 58 / Number 3 / November 1975 / Pages 314-320

Technical Paper / dx.doi.org/10.13182/NSE75-A26780

Stability of Moments in a Simple Neutronic System with Stochastic Parameters

Karmeshu, N. K. Bansal

Nuclear Science and Engineering / Volume 58 / Number 3 / November 1975 / Pages 321-327

Technical Paper / dx.doi.org/10.13182/NSE75-A26781

Macroscopic Representation of the Anisotropic Neutron Flux Spectrum and a New Greuling-Goertzel Approximation

Yasunori Yamamura

Nuclear Science and Engineering / Volume 58 / Number 3 / November 1975 / Pages 328-331

Technical Note / dx.doi.org/10.13182/NSE75-A26782

Neutron-Induced Gamma-Ray Production in Zinc for Incident-Neutron Energies of 4.9, 5.4, and 5.9 MeV

J. K. Dickens

Nuclear Science and Engineering / Volume 58 / Number 3 / November 1975 / Pages 331-338

Technical Note / dx.doi.org/10.13182/NSE75-A26783

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