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Volume 16

Number 1

Table of Contents
The Kinetic Behavior of the Coupled Regions of the UTR-10 Reactor(Richard A. Danofsky, Robert E. Uhrig)
The Convergence of the Equipoise Method(G. K. Kristiansen)
Reactor Dynamics with Reactivity Loss Rate Proportional to Energy(J. Ernest Wilkins, JR.)
Sintering of UO₂ in Carbon Dioxide Atmosphere(I. Amato, R. L. Colombo, A. M. Protti)
A Remark on the Measurement of the Diffusion Coefficient for Thermal Neutrons(Henry C. Honeck, Paul Michael)
Re: A Remark on the Measurement of the Diffusion Coefficient for Thermal Neutrons(N. P. Baumann)
1960 Nuclear Data Tables; Part 4, Short Tables(A. B. Smith)
The Collected Papers of Enrico Fermi, Volume 1, Italy 1921–1938(Robert R. Wilson)
Radiation Chemistry of Polymeric Systems(Vincent P. Calkins)

Surface Electrical Studies of Plutonia and Thoria Suspensions, Part I

R. G. Sowden, K. E. Francis

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE63-A26473

Surface Electrical Studies of Thoria and Plutonia Suspensions, Part II

R. G. Sowden, B. R. Harder, K. E. Francis

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 12-24

Technical Paper / dx.doi.org/10.13182/NSE63-A26474

A Mathematical Model for the Solvent Extraction of Uranyl Nitrate and Nitric Acid

M. H. Lletzke, R. W. Stoughton, Marjorie P. Lietzke

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 25-30

Technical Paper / dx.doi.org/10.13182/NSE63-A26475

Effects of Boundary Layer Turbulence Promoters on the Local Film Coefficients of ML-1 Fuel Elements

N. Kattchee, W. V. Mackewicz

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 31-38

Technical Paper / dx.doi.org/10.13182/NSE63-A26476

Neutron Temperatures in a CANDU-Type Power Reactor

B. G. Chidley, R. B. Turner, C. B. Bigham

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 39-67

Technical Paper / dx.doi.org/10.13182/NSE63-A26477

The Slowing-Down Spectrum in a CANDU-Type Reactor

C. B. Bigham, B. G. Chidley, R. B. Turner

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 68-84

Technical Paper / dx.doi.org/10.13182/NSE63-A26478

Neutron Temperature Distributions in a Cylinder of Hot Moderator

C. B. Bigham, R. B. Turner, B. G. Chidley

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 85-100

Technical Paper / dx.doi.org/10.13182/NSE63-A26479

A Method of Solving the Time Dependent Neutron Thermalization Problem

J. U. Koppel

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 101-110

Technical Paper / dx.doi.org/10.13182/NSE63-A26480

On the Estimation of Flux at a Point by Monte Carlo

M. H. Kalos

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 111-117

Technical Paper / dx.doi.org/10.13182/NSE63-A26481

Probability Distribution of Neutrons and Precursors in Multiplying Medium

George I. Bell, W. A. Anderson, D. Galbraith

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 118-123

Technical Paper / dx.doi.org/10.13182/NSE63-2

An Absolute Measurement of of Cf²⁵²

I. Asplund-Nilsson, H. Condé, N. Starfelt

Nuclear Science and Engineering / Volume 16 / Number 1 / May 1963 / Pages 124-130

Technical Paper / dx.doi.org/10.13182/NSE63-A26483

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