American Nuclear Society

/Create an Account

Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 59 / Number 1

Volume 59

Number 1

Table of Contents
Comments on “Analysis of the Microfission Reactor Concept”(F. Winterberg)
Reply to “Comments on ‘Analysis of the Microfission Reactor Concept’”(R. K. Cole, Jr., J. H. Renken)
From Scientific Search to Atomic Industry(Karl Cohen)
Nuclear-Reactor Analysis(G. C. Pomraning)

Analysis of Pressure Pulse Generation Due to Gas Release from Failed Fuel Pins in a Liquid-Metal Fast Breeder Reactor

Mujid S. Kazimi

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE76-A26803

Neutron Capture Cross Section of Niobium-93 from 2.6 to 700 keV

R. L. Macklin

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 12-20

Technical Paper / dx.doi.org/10.13182/NSE76-A26804

Criticality Safety Data Applicable to Processing Liquid-Metal Fast Breeder Reactor Fuel

R. C. Lloyd, E. D. Clayton

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 21-26

Technical Paper / dx.doi.org/10.13182/NSE76-A26805

Transfer Matrix Treatments for Multigroup Monte Carlo Calculations—The Elimination of Ray Effects

L. L. Carter, C. A. Forest

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 27-45

Technical Paper / dx.doi.org/10.13182/NSE76-A26806

Analysis and Comparison of Plutonium-238 Nuclear Data

M. Caner, S. Yiftah

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 46-50

Technical Note / dx.doi.org/10.13182/NSE76-A26807

The Slow-Neutron Fission Cross Sections of the Common Fissile Nuclides (Revised 1975)

C. B. Bigham

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 50-52

Technical Note / dx.doi.org/10.13182/NSE76-A26808

The Discrete Eigenvalue Problem for Azimuthally Dependent Transport Theory

J. Kenneth Shultis, T. R. Hill

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 53-56

Technical Note / dx.doi.org/10.13182/NSE76-A26809

Neutron Transport with Temperature Feedback

A. Belleni-Morante

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 56-58

Technical Note / dx.doi.org/10.13182/NSE76-A26810

Multigroup Representations of Slowing-Down Kernels in H₂O

Milton C. Edlund, Richard B. Jones, P. F. Zweifel

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 58-60

Technical Note / dx.doi.org/10.13182/NSE76-A26811

On the Generalized Perturbation Methods in Time-Dependent Problems

A. Gandini

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 60-63

Technical Note / dx.doi.org/10.13182/NSE76-A26812

A Finite Element Synthesis Method

Shi-tien Yang, A. F. Henry

Nuclear Science and Engineering / Volume 59 / Number 1 / January 1976 / Pages 63-67

Technical Note / dx.doi.org/10.13182/NSE76-A26813

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use