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Volume 50

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Nuclear Science and Engineering / Volume 50 / Number 1

January 1973

Table of Contents

Nuclear Science and Engineering / Volume 50 / Number 2

February 1973

Table of Contents

Nuclear Science and Engineering / Volume 50 / Number 4

April 1973

Table of Contents

Nuclear Science and Engineering / Volume 50 / Number 3

March 1973

Two-Group Critical Problems for Slabs and Spheres in Neutron-Transport Theory

J. T. Kriese, C. E. Siewert, Y. Yener

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 3-9

January 1973

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Neutron Transport for a Slab with a Degenerate Scattering Kernel

H. A. Larson, N. J. McCormick

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 10-19

January 1973

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Improved Moment Method Calculations of Gamma-Ray Transport: Application to Point Isotropic Sources in Water

L. V. Spencer, G. L. Simmons

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 20-31

January 1973

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Moments Method Calculation of Buildup Factors for Point Isotropic Monoenergetic Gamma-Ray Sources at Depths Greater than 20 Mean-Free-Paths

E. E. Morris

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 32-37

January 1973

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A Pulsed Neutron Experiment with Beryllium by the Use of a Gamma-Ray Flash from an Electron Linear Accelerator

Otohiko Aizawa, Hiroyuki Kadotani, Keiji Kanda, Yoshiaki Fujita

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 38-45

January 1973

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On the Use of Maximum Principle in Optimal Xenon Shutdown Problems

Seppo Salo

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 46-52

January 1973

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Analysis of the Coolant Behavior Following Fuel Failure and Molten Fuel-Sodium Interaction in a Fast Nuclear Reactor

A. W. Cronenberg, H. K. Fauske, D. T. Eggen

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 53-62

January 1973

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Sensitivity Analysis of Ideal Centrifuge Cascade for Producing Slightly Enriched Uranium

Toshio Kawai, Kotaro Inoue, Hiroshi Motoda, Tomofumi Kobayashi, Takashi Kiguchi

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 63-72

January 1973

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Monte Carlo Confidence Limits for Iterated-Source Calculations

D. B. MacMillan

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 73-75

January 1973

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Studies in Spectral Neutron Flux Synthesis

Harold Greenspan

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 75-78

January 1973

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The Effective Cross Section for the 16O(d, n)17 F Reaction for Fission Neutrons Moderated by Heavy Water

H. S. Pruys, B. D. Ganapol

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 79-80

January 1973

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Revised Delayed-Neutron Yield Data

A. E. Evans, M. M. Thorpe, M. S. Krick

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 80-82

January 1973

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Merit Index for Gas-Cooled Reactor Heat Transfer

G. Melese-d’Hospital

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 83-85

January 1973

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Thermal Characterization of Restructured Fuel

Aaron J. Friedland

Nuclear Science and Engineering / Volume 50 / Number 1 / Pages 85-87

January 1973

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A Program for Calculating Thermal Neutron Scattering Kernels

A. G. Gibbs, C. W. Lindenmeier

Nuclear Science and Engineering / Volume 50 / Number 1 / Page 88

January 1973

Nuclear Radiation Physics

Newton Underwood

Nuclear Science and Engineering / Volume 50 / Number 1 / Page 89

January 1973

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