Home / Publications / Journals / Nuclear Science and Engineering / Volume 58

Volume 58

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Number 1

Table of Contents
The New Heat Transfer(C. J. Hsu)
Activation Analysis with Neutron Generators(Vincent P. Guinn)
Functional-Analytic Concepts and Structures of Neutron Transport Theory(Edward Larsen)

A Method of Calculating the Effect of Clad Ballooning on Loss-of-Coolant-Accident Temperature Transients

P. C. Hall, R. B. Duffey

Nuclear Science and Engineering / Volume 58 / Number 1 / September 1975 / Pages 1-20

Technical Paper / dx.doi.org/10.13182/NSE75-A26763

The Recovery of Coolant Flow Following Rapid Release of Fission Gas from a Postulated Multiple Pin Failure in a Liquid-Metal Fast Breeder Reactor Subassembly

T. C. Chawla, G. M. Hauser, M. A. Grolmes, H. K. Fauske

Nuclear Science and Engineering / Volume 58 / Number 1 / September 1975 / Pages 21-32

Technical Paper / dx.doi.org/10.13182/NSE75-A26764

Analysis of Neutron Scattering and Gamma-Ray Production Integral Experiments on Carbon for Neutron Energies from 1 to 15 MeV

S. N. Cramer, E. M. Oblow

Nuclear Science and Engineering / Volume 58 / Number 1 / September 1975 / Pages 33-53

Technical Paper / dx.doi.org/10.13182/NSE75-A26765

Effect of Equivalence on Calculations of the Doppler Effect in Thin Lumped Absorbers

James W. Baughn, Rudolph Sher

Nuclear Science and Engineering / Volume 58 / Number 1 / September 1975 / Pages 54-63

Technical Paper / dx.doi.org/10.13182/NSE75-A26766

Activation Measurements of the Doppler Effect in Thin Uranium-238 Metal at up to 1000 K

James W. Baughn, Rudolph Sher

Nuclear Science and Engineering / Volume 58 / Number 1 / September 1975 / Pages 64-74

Technical Paper / dx.doi.org/10.13182/NSE75-A26767

Reactor Lattice Calculations with a Degenerate Neutron Thermalization Kernel

R. M. Versluis, A. J. Mockel

Nuclear Science and Engineering / Volume 58 / Number 1 / September 1975 / Pages 75-88

Technical Paper / dx.doi.org/10.13182/NSE75-A26768

Grain Structure of High-Temperature Gas-Cooled Reactor Fuel and Its Influence on the Effective Resonance Integral A Test of Calculations with the Aid of a Slowing-Down Spectrometer

H. Jonas, R. Hecker, M. Kloth

Nuclear Science and Engineering / Volume 58 / Number 1 / September 1975 / Pages 89-95

Technical Note / dx.doi.org/10.13182/NSE75-A26769

Telegrapher’s Equation Analysis of the Cooling Effect of a Cavity on the Fast Neutron Spectra

Katsuhisa Kudo, Masakuni Narita, Yasutomo Ozawa

Nuclear Science and Engineering / Volume 58 / Number 1 / September 1975 / Pages 95-98

Technical Note / dx.doi.org/10.13182/NSE75-A26770

Moderating Parameters for a Monoenergetic Source and a Fission Source

Yasunori Yamamura, Hiroshi Kimura

Nuclear Science and Engineering / Volume 58 / Number 1 / September 1975 / Pages 98-103

Technical Note / dx.doi.org/10.13182/NSE75-A26771

Number 2

Table of Contents
Deposition of Energy in U, UC, and UO₂ Fuels(K. B. Winterbon)
Comments on ‘Finite-Element Methods for Reactor Analysis,’(J. P. Hennart)
Comments on “Spectrum of Delayed Neutrons from the Thermal-Neutron Fission of Uranium-235”(G. Fieg, M. Lalovic, G. Woodruff)
Comment on “Influence of Deep Minima on Multigroup Cross-Section Generation”(Dermott E. Cullen)
Response to “Comment on ‘Influence of Deep Minima on Multigroup Cross-Section Generation’”(Martin Becker)

The Technological Requirements for Power by Fusion

D. Steiner

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 107-165

Critical Review / dx.doi.org/10.13182/NSE75-A28219

High-Order Response Matrix Equations in Two-Dimensional Geometry

Zbigniew Weiss, Sten-Örjan Lindahl

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 166-181

Technical Paper / dx.doi.org/10.13182/NSE75-1

A Leakage Iterative Method for Solving the Three-Dimensional Neutron Diffusion Equation

Y. Naito, M. Maekawa, K. Shibuya

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 182-192

Technical Paper / dx.doi.org/10.13182/NSE75-A28221

A Numerical Method for Solving Integral Equations of Neutron Transport—II

Sudarshan K. Loyalka, Robert W. Tsai

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 193-202

Technical Paper / dx.doi.org/10.13182/NSE75-A28222

A Two-Dimensional Finite Element Method for Integral Neutron Transport Calculations

E. E. Lewis, W. F. Miller, Jr., T. P. Henry

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 203-212

Technical Paper / dx.doi.org/10.13182/NSE75-A28223

The Resonance Integral of Coated Particles

Keiichiro Tsuchihashi, Yorio Gotoh

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 213-225

Technical Paper / dx.doi.org/10.13182/NSE75-A28224

Measurement of the Neutron and Gamma-Ray Spectra Originating from a 14-MeV Neutron Source in Liquid Nitrogen and Liquid Air

B. Bröcker, K. Clausen, P. Schneider-Kühnle, M. Weinert

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 226-238

Technical Paper / dx.doi.org/10.13182/NSE75-A28225

The Transport of Radioactive Corrosion Products in High-Temperature Water—I. Recirculating loop Experiments

D. H. Lister

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 239-251

Technical Paper / dx.doi.org/10.13182/NSE75-A28226

First-Flight Escape Probability for a Three-Region Spherical Body

M. M. R. Williams

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 252-253

Technical Note / dx.doi.org/10.13182/NSE58-252TN

On the Critical Reactor Problem for a Reflected Slab

C. E. Siewert, A. R. Burkart

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 253-255

Technical Note / dx.doi.org/10.13182/NSE75-A28228

The Ratio of the Uranium-238 to Uranium-235 Fission Cross Sections from 5.3 to 10.3 MeV

J. W. Meadows

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 255-257

Technical Note / dx.doi.org/10.13182/NSE75-A28229

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

Number 4

Table of Contents
Nuclear Power Plant Design Analysis(J. L. Meem)

Analysis of the Microfission Reactor Concept

Randall K. Cole, Jr., James H. Renken

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 345-353

Technical Paper / dx.doi.org/10.13182/NSE75-A26790

Resonance Region Analysis Without Resonance Parameters

S. Pearlstein

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 354-360

Technical Paper / dx.doi.org/10.13182/NSE75-A26791

Absorption Cross-Section Measurements for Californium-252 Spontaneous Fission Neutrons

L. Green

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 361-370

Technical Paper / dx.doi.org/10.13182/NSE75-A26792

Fission Cross Section of Uranium-235 from 0.8 to 4 MeV

J. B. Czirr, G. S. Sidhu

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 371-376

Technical Paper / dx.doi.org/10.13182/NSE75-A26793

Analytical Representation of Some Fast-Neutron Cross Sections Useful in Dosimetry

W. G. Cross, H. Ing

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 377-386

Technical Paper / dx.doi.org/10.13182/NSE75-A26794

Measured and Calculated Fission-Product Poisoning in Neutron-Irradiated Uranium-233

S. B. Gunst, J. C. Connor, D. E. Conway

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 387-413

Technical Paper / dx.doi.org/10.13182/NSE75-A26795

Mass Yields in the Fission of Uranium-235 and Plutonium-239 in the Neutron Spectrum of a Gas-Cooled Fast Reactor

M. Rajagopalan, H. S. Pruys, A. Grütter, H. R. von Gunten, E. A. Hermes, R. Richmond, E. Rössler, A. Schmid, P. Wydler

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 414-419

Technical Paper / dx.doi.org/10.13182/NSE75-A26796

Spectra and Dosimetry of Neutrons from Various Sources Shielded by Iron

H. Ing, W. G. Cross

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 420-430

Technical Paper / dx.doi.org/10.13182/NSE75-A26797

Gamma-Ray Intensities for the Radioactive Decay of Barium-140 and Lanthanum-140

J. T. Harvey, J. L. Meason, J. C. Hogan, H. L. Wright

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 431-435

Technical Paper / dx.doi.org/10.13182/NSE75-A26798

New Continuous Slowing-Down Theory for Resonance and Anisotropic Elastic Scattering

Shin-ichi Itoh, Hisashi Yamamoto

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 436-445

Technical Note / dx.doi.org/10.13182/NSE75-A26799

Sensitivity of the Lumped Fission-Product Model to Different Fission-Product Cross-Section Libraries

D. Ilberg, D. Saphier, S. Yiftah

Nuclear Science and Engineering / Volume 58 / Number 4 / December 1975 / Pages 445-449

Technical Note / dx.doi.org/10.13182/NSE75-A26800