ANS / Publications / Journals / Nuclear Science and Engineering

Iterative and Direct Approaches to the Critical Dominant Eigenfunction in Three-Dimensional Neutron Transport

F. Premuda, G. Spiga

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 1-8

Technical Paper / dx.doi.org/10.13182/NSE77-A26998

Monte Carlo Treatment of Fundamental-Mode Neutron Leakage in the Presence of Voids

Ely M. Gelbard, Richard Lell

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 9-23

Technical Paper / dx.doi.org/10.13182/NSE77-A26999

Neutron Wave Propagation Across a Temperature Discontinuity

Ashok Kumar, N. K. Saxena, L. S. Kothari

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 24-30

Technical Paper / dx.doi.org/10.13182/NSE77-A27000

Neutron Kinetics of Highly Compressed Fissionable Pellets

J. Ligou

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 31-40

Technical Paper / dx.doi.org/10.13182/NSE77-A27001

Origin of Protons in Californium-252 Fission

John A. Adams, R. R. Roy

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 41-47

Technical Paper / dx.doi.org/10.13182/NSE77-A27002

Neutron and Gamma Radiation from a Nitrogen Sphere Surrounding a D-T Neutron Source

G. S. Sidhu, W. E. Farley, L. F. Hansen, T. Komoto, B. Pohl, C. Wong

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 48-54

Technical Paper / dx.doi.org/10.13182/NSE77-A27003

A Comparison of the Gamma-Ray Spectra from 2.8-keV Neutron Capture and Thermal-Neutron Capture in Sodium-23

W. M. Wilson, H. E. Jackson, G. E. Thomas

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 55-62

Technical Paper / dx.doi.org/10.13182/NSE77-A27004

Structure-Fluid Interaction Between a Vibrating Wall and Flow in a Channel

R. A. Bajura, A. H. Mace, Jr.

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 63-74

Technical Paper / dx.doi.org/10.13182/NSE77-A27005

Steady-State Natural Circulation Performance of the Experimental Breeder Reactor II Primary Heat Transport Circuit

Ralph M. Singer, Jerry L. Gillette, Gerald H. Golden, Dale Mohr, Wayne K. Lehto, Charles C. Price, John I. Sackett

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 75-82

Technical Paper / dx.doi.org/10.13182/NSE77-A27006

The Effect of Niobium Additions on the Corrosion Behavior of Zircaloy-4

G. P. Sabol, S. G. McDonald

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 83-90

Technical Paper / dx.doi.org/10.13182/NSE77-A27007

Selection of Angular Quadrature for Anisotropic Transport Computations

Wayne J. Mikols, J. Kenneth Shultis

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 91-95

Technical Note / dx.doi.org/10.13182/NSE77-A27008

On the Inverse Problem for Multigroup Neutron Transport Theory

C. E. Siewert, M. N. Özişik, Y. Yener

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 95-96

Technical Note / dx.doi.org/10.13182/NSE77-A27009

Rapid Method of Calculating the Fluence and Spectrum of Neutrons from a Critical Assembly and the Resulting Dose

Joseph Bessis

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 96-101

Technical Note / dx.doi.org/10.13182/NSE77-A27010

Neutron-Induced Gamma-Ray Production in Lead-208 for Incident-Neutron Energies Between 4.9 and 8.0 MeV and in Bismuth-209 for an Incident-Neutron Energy of 5.4 MeV

J. K. Dickens

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 101-109

Technical Note / dx.doi.org/10.13182/NSE77-A27011