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Home / Publications / Journals / Nuclear Science and Engineering / Volume 7 / Number 1

Volume 7

Number 1

Reactivity Effects of Large Voids in the Reflector of a Light-Water-Moderated and -Reflected Reactor

A. B. Reynolds, T. J. Thompson, K. M. Henry, E. B. Johnson

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 1-13

Technical Paper / dx.doi.org/10.13182/NSE60-A25691

The Slowing Down of Neutrons by Deuterium

M. M. Levine, K. E. Roach, D. B. Wehmeyer, P. F. Zweifel

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 14-20

Technical Paper / dx.doi.org/10.13182/NSE60-A25692

Steels for Nuclear Reactors

H. F. Beeghly

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 21-25

Technical Paper / dx.doi.org/10.13182/NSE60-A25693

An Accurate Transfer Function for the Dynamic Analysis of Temperature and Heat Release in Cylindrical Fuel Elements

Modesto Iriarte, Jr.

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 26-32

Technical Paper / dx.doi.org/10.13182/NSE60-A25694

Approximate Solutions of the Reactor Kinetic Equations for Ramp Inputs

John MacPhee

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 33-43

Technical Paper / dx.doi.org/10.13182/NSE60-A25695

Enriched-Uranium Hydride Critical Assemblies

G. A. Linenberger, J. D. Orndoff, H. C. Paxton

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 44-57

Technical Paper / dx.doi.org/10.13182/NSE60-A25696

Integral Transport Theory of Thermal Utilization Factor in Infinite Slab Geometry

Michel H. Theys

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 58-63

Technical Paper / dx.doi.org/10.13182/NSE60-A25697

Space-Dependent Prompt Kinetics of a Subcritical Reactor

Joseph Agresta, Lyle B. Borst

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 64-68

Technical Paper / dx.doi.org/10.13182/NSE60-A25698

An Approximate Method for Treating Neutron Slowing Down

Gerald Goertzel, Eugene Greuling

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 69-72

Technical Paper / dx.doi.org/10.13182/NSE60-A25699

OMR Flat Plate Fuel Element Fabrication

G. V. Alm, E. E. Garrett, M. H. Binstock

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 73-82

Technical Paper / dx.doi.org/10.13182/NSE60-A25700

Development of Centrifugal Pumps for Operation with Liquid Metals and Molten Salts at 1100–1500°F

A. G. Grindell, W. F. Boudreau, H. W. Savage

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 83-91

Technical Paper / dx.doi.org/10.13182/NSE60-A25701

 

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