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Volume 70

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Nuclear Science and Engineering / Volume 70 / Number 1

April 1979

Table of Contents

Nuclear Science and Engineering / Volume 70 / Number 2

May 1979

Table of Contents

Nuclear Science and Engineering / Volume 70 / Number 3

June 1979

Optimal Choice of Parameters for Exponential Biasing in Monte Carlo

A. Dubi, Donald J. Dudziak

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 1-13

April 1979

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Bounded Flux-at-a-Point Estimators for Multigroup Monte Carlo Computer Codes

S. K. Fraley, T. J. Hoffman

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 14-19

April 1979

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Development of Depletion Perturbation Theory for Coupled Neutron/Nuclide Fields

M. L. Williams

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 20-36

April 1979

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PURNIMA—A PuO2-Fueled Zero-Energy Fast Reactor at Trombay

P. K. Iyengar, T. K. Basu, K. Chandramoleshwar, S. Das, P. K. Job, S. K. Kapil, V. R. Nargundkar, C. S. Pasupathy, M. Srinivasan, K. Subba Rao

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 37-52

April 1979

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Neutron Capture Cross Sections of Rhodium, Thulium, Iridium, and Gold Between 0.5 and 3.0 MeV

S. Joly, J. Voignier, G. Grenier, D. M. Drake, L. Nilsson

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 53-59

April 1979

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Diagnostic Neutron Spectra from Deuterons on Several Materials

H. W. Lefevre, J. C. Davis, J. D. Anderson

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 60-65

April 1979

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Transitor Damage Characterization by Neutron Displacement Cross Section in Silicon: Experimental

V. V. Verbinski, C. Cassapakis, R. L. Pease, H. L. Scott

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 66-72

April 1979

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Diffusion Coefficients of Sodium Vapors in Argon and Helium

T. Kumada, R. Ishiguro, Y. Kimachi

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 73-81

April 1979

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An Atomic Model for Neutral and Singly Ionized Uranium

Edward L. Maceda, George H. Miley

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 82-95

April 1979

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Three Basic Neutron-Transport Problems in Spherical Geometry

C. E. Siewert, P. Grandjean

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 96-98

April 1979

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The Total Neutron Cross Section of Boron-10 Between 90 and 420 keV

H. Beer, R. R. Spencer

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 98-101

April 1979

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Fission Yields for Fast-Neutron Fission of Uranium-238

J. E. Gindler, L. E. Glendenin, J. W. Meadows, Jr., K. F. Flynn

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 101-106

April 1979

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Identifiability of Dynamics of a Boiling Water Reactor Using Autoregressive Modeling

Masaharu Kitamura, Kunihiko Matsubara, Ritsuo Oguma

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 106-110

April 1979

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A Semi-Analytic Solution to the Transport Equation in Spherical Geometry

A. Dubi, Y. S. Horowitz

Nuclear Science and Engineering / Volume 70 / Number 1 / Page 111

April 1979

Effects of Energy Losses of Arbitrary Magnitude on Fuel Quality, Vapor Density, and Bubble Diameter in an Idealized Expansion of Mixtures of UO2 and Sodium

Hugo W. Bertini, Janice S. White

Nuclear Science and Engineering / Volume 70 / Number 1 / Page 111

April 1979

Higher Order Time-Dependent Generalized Perturbation Theory

A. Gandini

Nuclear Science and Engineering / Volume 70 / Number 1 / Page 112

April 1979

Thermal Effluent Disposal from Power Generation

Richard F. Cole

Nuclear Science and Engineering / Volume 70 / Number 1 / Pages 113-114

April 1979

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