Volume 46

Number 3

Table of Contents
MECC-3, A Monte Carlo Intranuclear-Cascade Code for Medium-Energy (<3500 MeV) Particle-Nucleus Collisions(H. W. Bertini, A. H. Culkowski, M. P. Guthrie, O. W. Hermann)
VIXEN(Donald J. Dudziak, Johnny M. Romero)
Dynamics of Nuclear Reactors(Allan F. Henry)
Monte Carlo Principles and Neutron Transport Problems(Robert R. Coveyou)
Nuclear Theory, Volume 1: Nuclear Models(K. T. Hecht)
Radiation Heat Transfer(C. L. Tien)
Nuclear Heal Transport(O. E. Dwyer, J. M. Hendrie)
New Method for Measurement of the Effective Fraction of Delayed Neutrons from Fission(J. T. Mihalczo)

Plasma Energy Deposition from Nuclear Elastic Scattering

Joseph J. Devaney, Myron L. Stein

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 323-333

Technical Paper / dx.doi.org/10.13182/NSE71-A22370

The Effect of the Ground on the Steady-State and Time-Dependent Transport of Neutrons and Secondary Gamma Rays in the Atmosphere

E.A. Straker

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 334-355

Technical Paper / dx.doi.org/10.13182/NSE71-A22371

Fast Neutron Total and Scattering Cross Sections of Uranium-238

P. Lambropoulos

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 356-365

Technical Paper / dx.doi.org/10.13182/NSE71-A22372

A New Solution of the Point Kinetics Equations

J. A. W. da Nóbrega

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 366-375

Technical Paper / dx.doi.org/10.13182/NSE71-A22373

Evaluation of Neutron Spectral Effects in a Plutonium-Fueled Lattice by Foil Activation

F. V. Orestano, F. Pistella

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 376-384

Technical Paper / dx.doi.org/10.13182/NSE71-A22374

Application of Nonlinear Programming to the Optimal Control of Point Model Nuclear Reactors

G. F. Malan, B. V. Koen

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 385-393

Technical Paper / dx.doi.org/10.13182/NSE71-A22375

Heated Laminar Gas Flow in Annuli with Temperature-Dependent Transport Properties

R. W. Shumway, D. M. McEligot

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 394-407

Technical Paper / dx.doi.org/10.13182/NSE71-A22376

Dynamic Effects in Radiation Diagnosis of Fluctuating Voids

A. A. Harms, C. F. Forrest

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 408-413

Technical Paper / dx.doi.org/10.13182/NSE71-A22377

Fission Temperatures as a Function of the Average Number of Neutrons from Fission

R. J. Howerton, R. J. Doyas

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 414-416

Technical Note / dx.doi.org/10.13182/NSE71-A22378

Neutron Diffusion from a Fast Point Source in Aqueous Absorbing Solutions

Dong H. Nguyen, Marshall T. Slayton, John A. Frew

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 416-421

Technical Note / dx.doi.org/10.13182/NSE71-A22379

Evaluation of Space-Energy Factorization for Two-Dimensional Diffusion Theory Problems in the Liquid Metal Fast Breeder Reactor

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 421-425

Technical Note / dx.doi.org/10.13182/NSE71-A22380

Roots and Coefficients from the Integral Solution of the Reactor Kinetic Equations Applicable to Uranium-235 Fueled, Heavy Water Moderated Reactors

Joseph S. Crudele, Richard A. Danofsky

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 425-427

Technical Note / dx.doi.org/10.13182/NSE71-A22381

Calculated Thermal (n, α) Cross Section for Nickel-59

G. J. Kirouac

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 427-428

Technical Note / dx.doi.org/10.13182/NSE71-A22382

On a Possible Resolution of the Nitrogen Nonelastic Neutron Cross-Section Discrepancy Below 9 MeV

F. G. Perey, W. E. Kinney

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 428-431

Technical Note / dx.doi.org/10.13182/NSE71-A22383

Critical Heat Fluxes of Full Flux Shapes from Partial Flux Shapes

R. H. Wilson, G. O. Geissler

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 431-436

Technical Note / dx.doi.org/10.13182/NSE71-A22384