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Number 1

Table of Contents
Activation Analysis with Neutron Generators (Vincent P. Guinn)
The New Heat Transfer (C. J. Hsu)
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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)
Annual Review of Nuclear Science (W. Bennett Lewis, Gordon C. Ball, H. C. Lee, I. S. Towner)
Albedo-Adjusted Fast-Neutron Diffusion Coefficients in Reactor Reflectors (William B. Terney)

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE75-A26800