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Volume 41 / Number 2

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Nuclear Science and Engineering / Volume 41 / Number 2

August 1970

Primary-Recoil Atom Spectra from ENDF/B Data

J. D. Jenkins

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 155-163

August 1970

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Neutron Spectrum Measurements in a Homogeneous Erbium System and Erbium Cross Sections

T. Gozani, G. D. Trimble

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 164-176

August 1970

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Neutron Fission Cross Sections for 231Th, 233Th, 235U, 237U, 239U, 241Pu, and 243Pu from 0.5 to 2.25 MeV Using (t, pf) Reactions

J. D. Cramer, H. C. Britt

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 177-187

August 1970

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Total Neutron Cross Section of Technetium-99 from 0.01 to 1000 eV

T. Watanabe, S. D. Reeder

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 188-192

August 1970

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A Unified Model of Deformed Odd-Odd Nuclei for Nuclear Data Generation and Analysis

C. Y. Fu, K. J. Yost

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 193-208

August 1970

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Reaction Rates in Representative Plutonium-Recycle Fuel Lattices

J. G. Carver, W. R. Morgan, C. R. Porter, M. A. Robkin

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 209-225

August 1970

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Linearly Anisotropic Extensions of Asymptotic Neutron Diffusion Theory

R. J. Doyas, B. L. Koponen

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 226-236

August 1970

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Truncation Error Analysis of Finite Difference Approximations to the Transport Equation

Wm. H. Reed, K. D. Lathrop

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 237-248

August 1970

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Spectral Synthesis Applied to Fast-Reactor Dynamics

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 249-258

August 1970

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Monte Carlo Method for Geometrical Perturbation and its Application to the Pulsed Fast Reactor

Hiroshi Takahashi

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 259-270

August 1970

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Hybrid Computer Solution of Thermal Energy Equations in Porous Fuels

W. W. Marr, M. M. El-Wakil

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 271-280

August 1970

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Transient Digital Control of a Boiling-Water Reactor Power Plant

W. Ciechanowicz, B. Lazarević

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 281-293

August 1970

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An Experimental Investigation of Absorption in the 1.056 eV Resonance of Plutonium-240

Charles J. Hulka, Gene L. Woodruff

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 294-296

August 1970

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Use of Californium-252 as a Randomly Pulsed Neutron Source for Prompt Neutron Decay Measurements

John T. Mihalczo

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 296-298

August 1970

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Gozani's Pulsed Neutron Technique with Repeated Recycling of Analyzer Between Bursts

R. H. Chow

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 298-299

August 1970

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An Implicit Method for Solving the Lumped Parameter Reactor-Kinetics Equations by Repeated Extrapolation

Masayuki Izumi, Takashi Noda

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 299-303

August 1970

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Interface Conditions for Discontinuous Flux Synthesis Methods

William B. Terney

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 303-307

August 1970

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A Slow Neutron Scattering Routine from the Gas Model

John R. Eriksson

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 307-309

August 1970

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Geometric Interpretation of the Function g(c,µ) of Neutron Transport Theory

Perry A. Newman, Robert L. Bowden

Nuclear Science and Engineering / Volume 41 / Number 2 / Pages 309-310

August 1970

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Price:$30.00
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