Home / Publications / Journals / Nuclear Science and Engineering / Volume 12 / Number 2

Volume 12

Number 2

Table of Contents
Transport Mean Free Path and Diffusion Length of Neutrons Calculated From Markov Chain Statistics(E. Richard Cohen)
Multiregion Fuel Elements(M. R. Fleishman, A. A. Strasser, J. E. Wilkins, Jr.)
Thermal Flux Disadvantage Factors for Slab Geometry(Chander P. Bhalla)
Slowing Down with Anisotropic Scattering(A. Keane, J. P. Pollard)
Introduction to Nuclear Engineering(Paul C. Zmola)
Protection Against Radiation(Karl Z. Morgan)
Reactor Heat Transfer(H. F. Poppendiek)
Numerical Methods for Nuclear Reactor Calculations(E. M. Gelbard)
Plasmas and Controlled Fusion(Norman Rostoker)
Reactors of the World—Second Series(Edward D. Jordan)
Introduction to Nuclear Engineering(Glen J. Schoessow)
Nuclear Reactors for Power Generation(V. E. Schrock)
Encyclopedic Dictionary of Electronics and Nuclear Engineering(S. H. Hanauer)
MIST(D. M. Shapiro)
GREEN(G. R. Dalton)
DETECTOR(G. R. Dalton)
TRAC-1(Jerome Spanier)

The Potential of Plutonium as a Fuel in Near-Thermal Converter Reactors

Karl H. Puechl

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 135-150

Technical Paper / dx.doi.org/10.13182/NSE62-A26051

The Potential of Plutonium as a Fuel in Near-Thermal Burner Reactors

KArl H. Puechl

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 151-156

Technical Paper / dx.doi.org/10.13182/NSE62-A26052

The Total Cross Section of Aluminium for Neutrons of Energies From 0.003 ev to 0.009 ev

D. Bally, S. Todireanu, S. Rîpeanu

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 157-159

Technical Paper / dx.doi.org/10.13182/NSE62-A26053

The Control System of the Ispra-1 Reactor

S. Barabaschi, A. Pulacci

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 160-168

Technical Paper / dx.doi.org/10.13182/NSE62-A26054

Neutron Capture to Fission Ratios in U²³³, U²³⁵, Pu²³³

J. C. Hopkins, B. C. Diven

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 169-177

Technical Paper / dx.doi.org/10.13182/NSE62-A26055

Backscattering of Gamma Rays

Tomonori Hyodo

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 178-184

Technical Paper / dx.doi.org/10.13182/NSE62-A26056

The Development of a Dilute Aluminum-Gold Alloy for Thermal and Resonance Neutron Flux Measurements

L. M. Howe, R. E. Jervis, T. A. Eastwood

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 185-189

Technical Paper / dx.doi.org/10.13182/NSE12-2-185

Measurement of Neutron Diffusion Parameters in Water by the Pulsed Neutron Method

W. M. Lopez, J. R. Beyster

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 190-202

Technical Paper / dx.doi.org/10.13182/NSE62-A26058

Thermoelastic Dynamics of Rods, Thin Shells, and Solid Spheres

David Burgreen

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 203-217

Technical Paper / dx.doi.org/10.13182/NSE62-A26059

Determination of Reactor Transfer Functions by Statistical Correlation Methods

V. Rajagopal

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 218-224

Technical Paper / dx.doi.org/10.13182/NSE62-A26060

The Performance of Metallic-Foil Insulations in Vertical Gas Spaces

R. E. MacPherson, Jr., H. D. Stuart

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 225-233

Technical Paper / dx.doi.org/10.13182/NSE62-A26061

Effectiveness of Lining Materials in Increasing the Blast Resistance of A Simulated Outer Containment Vessel for A Nuclear Reactor

J. W. Hanna, W. O. Ewing, Jr.

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 234-237

Technical Paper / dx.doi.org/10.13182/NSE62-A26062

Neutron Diffusion in a Temperature Gradient

J. R. L. de Ladonchamps, L. M. Grossman

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 238-242

Technical Paper / dx.doi.org/10.13182/NSE62-A26063

Total Neutron Cross Section of Pa²³¹

F. B. Simpson, W. H. Burgus, J. E. Evans, H. W. Kirby

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 243-249

Technical Paper / dx.doi.org/10.13182/NSE62-A26064

The Scattering of Thermal Neutrons by Moderators

P. A. Egelstaff

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 250-259

Technical Paper / dx.doi.org/10.13182/NSE62-A26065

On the Evaluation of the Thermal Neutron Scattering Law

P. A. Egelstaff, P. Schofield

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 260-270

Technical Paper / dx.doi.org/10.13182/NSE62-A26066

An Instrument for Nondestructively Testing Fuel Core to Cladding Heat Transfer

Donald R. Green

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 271-275

Technical Paper / dx.doi.org/10.13182/NSE62-A26067

A Three-Dimensional Depletion Analysis of the First Shippingport Pressurized Water Reactor

D. H. Jones, R. P. Christman

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 276-284

Technical Paper / dx.doi.org/10.13182/NSE62-A26068

Cesium Exchange Properties of Vermiculite

D. G. Jacobs

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 285-292

Technical Paper / dx.doi.org/10.13182/NSE62-A26069

Effective Resonance Integral of Thorium Metal

Alan B. Rothman, Charles E. W. Ward

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 293-300

Technical Paper / dx.doi.org/10.13182/NSE62-A26070

Measurement of the Dancoff Correction

J. Hardy, Jr., G. G. Smith, J. A. Mitchell, D. Klein

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 301-308

Technical Paper / dx.doi.org/10.13182/NSE62-A26071