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Volume 59

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Nuclear Science and Engineering / Volume 59 / Number 2

February 1976

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Fast-Neutron Total and Scattering Cross Sections of Elemental Nickel

P. Guenther, A. Smith, J. Whalen

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 106-116

February 1976

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Uncertainty Analysis of Fission-Product Decay-Heat Summation Methods

F. Schmittroth

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 117-139

February 1976

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Boundary-Value Thermal-Hydraulic Analysis of a Reactor Fuel Rod Bundle

William T. Sha, Robert C. Schmitt, P. R. Huebotter

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 140-160

February 1976

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A Monte Carlo Code for the Evaluation of the Thermal Design of a Nuclear Reactor Core

Kazuyoshi Miki, Kotaro Inoue

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 161-169

February 1976

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Generalized Padé and Chebyshev Approximations for Point Kinetics

J. P. Hennart, B. Torres Barrios

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 170-187

February 1976

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Sensitivity Theory from a Differential Viewpoint

E. M. Oblow

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 187-189

February 1976

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Cross-Section Sensitivity of the D-T Fusion Probability and the D-T and T-T Reaction Rates

R. T. Santoro, J. Barish

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 189-194

February 1976

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Neutron Slowing Down with Energy-Dependent Anisotropy of Scattering

D. Stefanović

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 194-198

February 1976

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Methods for Detailed Thermal and Hydraulic Analysis of Water-Cooled Reactors

Joel Weisman, Robert W. Bowring

Nuclear Science and Engineering / Volume 59 / Number 2 / Page 199

February 1976

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

B. Frogner, L. M. Grossman

Nuclear Science and Engineering / Volume 59 / Number 2 / Page 199

February 1976

Table of Contents

Nuclear Science and Engineering / Volume 59 / Number 1

January 1976

Analysis of Pressure Pulse Generation Due to Gas Release from Failed Fuel Pins in a Liquid-Metal Fast Breeder Reactor

Mujid S. Kazimi

Nuclear Science and Engineering / Volume 59 / Number 1 / Pages 1-11

January 1976

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Neutron Capture Cross Section of Niobium-93 from 2.6 to 700 keV

R. L. Macklin

Nuclear Science and Engineering / Volume 59 / Number 1 / Pages 12-20

January 1976

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Criticality Safety Data Applicable to Processing Liquid-Metal Fast Breeder Reactor Fuel

R. C. Lloyd, E. D. Clayton

Nuclear Science and Engineering / Volume 59 / Number 1 / Pages 21-26

January 1976

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Transfer Matrix Treatments for Multigroup Monte Carlo Calculations—The Elimination of Ray Effects

L. L. Carter, C. A. Forest

Nuclear Science and Engineering / Volume 59 / Number 1 / Pages 27-45

January 1976

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Analysis and Comparison of Plutonium-238 Nuclear Data

M. Caner, S. Yiftah

Nuclear Science and Engineering / Volume 59 / Number 1 / Pages 46-50

January 1976

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The Slow-Neutron Fission Cross Sections of the Common Fissile Nuclides (Revised 1975)

C. B. Bigham

Nuclear Science and Engineering / Volume 59 / Number 1 / Pages 50-52

January 1976

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The Discrete Eigenvalue Problem for Azimuthally Dependent Transport Theory

J. Kenneth Shultis, T. R. Hill

Nuclear Science and Engineering / Volume 59 / Number 1 / Pages 53-56

January 1976

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