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Volume 110 / Number 3

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Nuclear Science and Engineering / Volume 110 / Number 3

March 1992

Dynamics and Power Prediction in Fission Bursts

T. F. Wimett

Nuclear Science and Engineering / Volume 110 / Number 3 / Pages 209-236

March 1992

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A Multidimensional Multigroup Diffusion Model for the Determination of the Frequency-Dependent Field of View of a Neutron Detector

T. H. J. J. van der Hagen, J. E. Hoogenboom, H. van Dam

Nuclear Science and Engineering / Volume 110 / Number 3 / Pages 237-253

March 1992

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Price:$30.00

Unbiased Combinations of Nonanalog Monte Carlo Techniques and Fair Games

Thomas E. Booth, Shane P. Pederson

Nuclear Science and Engineering / Volume 110 / Number 3 / Pages 254-261

March 1992

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Price:$30.00

Boundary Conditions to Describe the Reactor Reflector

E. Temesvári, M. Makai

Nuclear Science and Engineering / Volume 110 / Number 3 / Pages 262-274

March 1992

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Distributed Neutron Sources in a Semi-Infinite Medium

Barry D. Ganapol

Nuclear Science and Engineering / Volume 110 / Number 3 / Pages 275-281

March 1992

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Absolute Measurements of the Fast Neutron Capture Cross Section of 238U

Eiping Quang, Glenn F. Knoll

Nuclear Science and Engineering / Volume 110 / Number 3 / Pages 282-288

March 1992

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Differential Neutron Production Cross Sections for 256-MeV Protons

M. M. Meier, W. B. Amian, C. A. Goulding, G. L. Morgan, C. E. Moss

Nuclear Science and Engineering / Volume 110 / Number 3 / Pages 289-298

March 1992

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Neutron Yields from Stopping-Length Targets for 256-MeV Protons

M. M. Meier, W. B. Amian, C. A. Goulding, G. L. Morgan, C. E. Moss

Nuclear Science and Engineering / Volume 110 / Number 3 / Pages 299-301

March 1992

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Comment on “Comment on the Physical Interpretation of the Flux”

J. D. Lewins

Nuclear Science and Engineering / Volume 110 / Number 3 / Page 302

March 1992

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