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Volume 42

Number 2

Time-Dependent Neutron Spectra Measurements in Water

J. H. Menzel, R. E. Slovacek, E. R. Gaerttner

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 119-136

Technical Paper / dx.doi.org/10.13182/NSE70-A19493

A Calculation of the Coherent Neutron Scattering from Polycrystalline Beryllium

G. M. Borgonovi, D. Sprevak

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 137-142

Technical Paper / dx.doi.org/10.13182/NSE70-A19494

Neutron Fission and Capture Cross-Section Measurements for Uranium-233 in the Energy Region 0.02 to 1 eV

L. W. Weston, R. Gwin, G. de Saussure, R. W. Ingle, J. H. Todd, C, W. Craven, R. W. Hockenbury, R. C. Block

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 143-149

Technical Paper / dx.doi.org/10.13182/NSE70-A19495

Exponential Experiments with Lattices of Uranium-233 Oxide and Thorium Oxide in Light and Heavy Water

H. H. Windsor, W. J. Tunney, G. A. Price

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 150-161

Technical Paper / dx.doi.org/10.13182/NSE70-2

Neutron Transmission Probabilities Across Control Blades Filled with Round Tubes: Formulation and Accuracy

M. Michelini

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 162-170

Technical Paper / dx.doi.org/10.13182/NSE70-A19497

On the Complete Eigenvalue Spectrum for the Neutron Wave Problem in Multigroup Diffusion Theory

A. K. Ghatak, N. K. Bansal, Om Pal Singh

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 171-178

Technical Paper / dx.doi.org/10.13182/NSE70-A19498

Conditional Variances Pertinent to Doppler Effect Studies

R. N. Hwang, L. B. Miller

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 179-190

Technical Paper / dx.doi.org/10.13182/NSE70-A19499

Fission Yields of Over 40 Stable and Long-Lived Fission Products for Thermal Neutron Fissioned 233U, 235U, 239Pu, and 241Pu and Fast Reactor Fissioned 235U and 239Pu

F. L. Lisman, R. M. Abernathey, W. J. Maeck, J. E. Rein

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 191-214

Technical Paper / dx.doi.org/10.13182/NSE70-A19500

Determination of Nuclear Fuel Burnup from Fission Product Analysis

F. L. Lisman, W. J. Maeck, J. E. Rein

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 215-219

Technical Paper / dx.doi.org/10.13182/NSE70-A19501

The Interaction of Neutronics and Acoustics in a Gaseous Core Nuclear Rocket

Harry McNeill, Martin Becker

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 220-229

Technical Paper / dx.doi.org/10.13182/NSE70-A19502

An Accurate Determination of the Value of the Hopf q-Function at Infinity

Wendell C. DeMarcus, Robert A. Stokes

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 230-231

Technical Note / dx.doi.org/10.13182/NSE70-A19503

A Numerical Calculation of the Milne Problem Extrapolation Length

E. Richard Cohen

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 231-232

Technical Note / dx.doi.org/10.13182/NSE70-A19504

Evaluation of the Mott Scattering Cross Section and the Goudsmit-Saunderson Multiple Scattering Distribution for Electron Transport Calculations

R. M. Felder

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 232-233

Technical Note / dx.doi.org/10.13182/NSE70-A19505

Calculation of Heterogeneous Fluxes and Reactivity Worths

W. M. Stacey, Jr.

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 233-236

Technical Note / dx.doi.org/10.13182/NSE70-A19506

Time-Step Length Errors in Digital Simulation of Spatial Xenon Oscillations

Claude G. Poncelet, Alan M. Christie

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 236-239

Technical Note / dx.doi.org/10.13182/NSE70-A19507

Xenon Oscillation Experiments in a Production Reactor

S. V. Topp, R. F. Byars, R. P. Germann

Nuclear Science and Engineering / Volume 42 / Number 2 / November 1970 / Pages 239-254

Technical Note / dx.doi.org/10.13182/NSE70-A19508