Home / Publications / Journals / Nuclear Science and Engineering / Volume 68 / Number 3

Volume 68

Number 3

Table of Contents
Annual Review of Nuclear Science(W. Bennett Lewis, William R. Conkie, W. McLatchie, B. C. Robertson, John C. Hardy, F. C. Khanna)
Flow Induced Vibration(D. J. Gorman)

The One-Group Neutron Transport Equation and Angular Flux Separability

D. Shalitin, J. J. Wagschal, Y. Yeivin

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 243-248

Technical Paper / dx.doi.org/10.13182/NSE78-A27303

Analytic Method for the Numerical Solution of the Integral Transport Equation for a Homogeneous Cylinder

Michael S. Milgram

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 249-269

Technical Paper / dx.doi.org/10.13182/NSE78-A27304

Statistical Model Analysis of Spin Influence on the Deexcitation of Fission Fragments

D. P. Min, M. Martinot

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 270-280

Technical Paper / dx.doi.org/10.13182/NSE78-A27305

Detailed Calculations in Energy and Space of Effective Neutron Resonance Cross Sections

José M. Aragonés

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 281-298

Technical Paper / dx.doi.org/10.13182/NSE78-A27306

The Impact of Aging Mechanisms on Reactor Safety System Performance

E. Oelkers, W. W. Weaver

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 299-307

Technical Paper / dx.doi.org/10.13182/NSE78-A27307

The Role of Rayleigh-Taylor Instabilities in Fuel-Coolant Interactions

Fred Cooper, John Dienes

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 308-321

Technical Paper / dx.doi.org/10.13182/NSE78-A27308

Sensitivity Theory for Reactor Thermal-Hydraulics Problems

E. M. Oblow

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 322-337

Technical Paper / dx.doi.org/10.13182/NSE78-A27309

Multidimensional Effects in Critical Two-Phase Flow

J. R. Travis, C. W. Hirt, W. C. Rivard

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 338-348

Technical Paper / dx.doi.org/10.13182/NSE78-A27310

Possible Criticality of Protactinium-231

George C. Wu, Lawrence Ruby

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 349-351

Technical Note / dx.doi.org/10.13182/NSE78-A27311

A Direct Technique for Unfolding Neutron Spectra from Activation Data

Hiroshi Sekimoto

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 351-356

Technical Note / dx.doi.org/10.13182/NSE78-A27312

Effects of Nuclear Deformation on Neutron Total Cross Sections

L. Zuffi

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 356-357

Technical Note / dx.doi.org/10.13182/NSE78-A27313

Measurements of the Total Neutron Cross Section of Uranium-233 Between 40 keV and 4.5 MeV

W. P. Poenitz, J. F. Whalen, P. Guenther, A. B. Smith

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 358-359

Technical Note / dx.doi.org/10.13182/NSE78-A27314

The Fission Cross Sections of Plutonium-239 and Plutonium-242 Relative to Uranium-235 from 0.1 to 10 MeV

J. W. Meadows

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 360-363

Technical Note / dx.doi.org/10.13182/NSE78-A27315

Best-Estimate Fuel Rod Modeling Techniques

D. A. Niebruegge, E. L. Tolman, C. W. Solbrig

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 363-368

Technical Note / dx.doi.org/10.13182/NSE78-A27316