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Volume 61

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Neutron Absorption Cross Section of Americium-241

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 356-365

November 1976

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Light Charged Particles and Fission Elements from Californium-252 Fission

Charles A. Bolig, Jr., R. R. Roy

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 366-369

November 1976

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Critical Experiments with Low-Moderated Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8, 15, and 30 wt% Plutonium

S. R. Bierman, E. D. Clayton

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 370-376

November 1976

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A Simple Approximate Treatment of Neutron Inelastic Scattering in a Fast Reactor Assembly

Yasunori Yamamura

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 377-387

November 1976

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Synthesis of an Elementary Function for the Spatially Dependent Neutron Slowing Down Distribution in Hydrogen

Harvey J. Amster, K. Cheuk Chan

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 388-398

November 1976

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Stability Analysis of Spatially Dependent Nonlinear Reactor Systems Using a Semigroup Approach

Ronald J. Onega, Lech Mync, John A. Burns

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 399-407

November 1976

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A Method of Characteristics and Other Improvements in Solution Methods for the Transport Equation

Bengt G. Carlson

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 408-425

November 1976

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Observation of a Difference in Yields of Delayed Neutron Emitters from U3O8 and UO2

H. R. Lukens, R. L. Bramblett

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 426-428

November 1976

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Critical Experiments and the 2200 m/sec Neutron Parameters

R. Gwin

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 428-431

November 1976

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Acceleration of the Convergence of the Integral Transform Method

V. C. Boffi, V. G. Molinari, G. Spiga

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 431-434

November 1976

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Generalized Exact Spatially Dependent Neutron Slowing Down Distribution Near Source Lethargy

K. Cheuk Chan, Harvey J. Amster

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 434-437

November 1976

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Control Algorithms in a Coarse-Mesh Rebalance Framework

M. V. Gregory, H. C. Honeck

Nuclear Science and Engineering / Volume 61 / Number 3 / Pages 437-445

November 1976

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Table of Contents

Nuclear Science and Engineering / Volume 61 / Number 2

October 1976

A Coarse-Mesh Correction of the Finite Difference Method for Neutron Diffusion Calculations

Yasuyoshi Kato, Toshikazu Takeda, Seiichi Takeda

Nuclear Science and Engineering / Volume 61 / Number 2 / Pages 127-141

October 1976

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Exact Solutions of the Neutron Slowing Down Equation

Trine-Yie Dawn, Chio-Min Yang

Nuclear Science and Engineering / Volume 61 / Number 2 / Pages 142-158

October 1976

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A Discrete Energy Formulation of Neutron Transport Theory Applied to Solving the Discrete Ordinates Equations

J. Ching, E. M. Oblow, H. Goldstein

Nuclear Science and Engineering / Volume 61 / Number 2 / Pages 159-169

October 1976

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Perturbation Theory and Importance Functions in Integral Transport Formulations

E. Greenspan

Nuclear Science and Engineering / Volume 61 / Number 2 / Pages 170-180

October 1976

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The Representation of Light-Water Reflectors by Boundary Conditions

P.C. Kalambokas, A. F. Henry

Nuclear Science and Engineering / Volume 61 / Number 2 / Pages 181-194

October 1976

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External Bremsstrahlung Generated by Yttrium-91 and Thallium-204 Beta Rays

K. V. N. Sarma, K. Narasimha Murty, V. V. V. Subrahmanyam

Nuclear Science and Engineering / Volume 61 / Number 2 / Pages 195-200

October 1976

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Calculations of the Neutron Emission Spectra from Materials Bombarded with 14-MeV Neutrons

L. F. Hansen, S. M. Grimes, R. J. Howerton, J D. Anderson

Nuclear Science and Engineering / Volume 61 / Number 2 / Pages 201-211

October 1976

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