ANS / Publications / Journals / Nuclear Science and Engineering

Analysis of the Zero Power Reactor Transfer Function

H. C. Corben

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 461-465

dx.doi.org/10.13182/NSE59-A15503

R. S. Stone, R. E. Slovacek

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 466-474

dx.doi.org/10.13182/NSE59-A15504

Complete Spherical Harmonics Solution of the Boltzmann Equation for Neutron Transport in Homogeneous Media with Cylindrical Geometry

Walter Kofink

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 475-486

dx.doi.org/10.13182/NSE59-A15505

Fission Fragment Impact Trapping by ThO₂ Slurry Particles

Donald G. Gardner

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 487-492

dx.doi.org/10.13182/NSE59-A15506

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. I. Introduction

L. Burris, H. M. Feder, S. Lawroski, W. A. Rodger, R. C. Vogel

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 493-495

dx.doi.org/10.13182/NSE59-A15507

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. II. Experimental Furnaces

G. J. Bernstein, G. A. Bennett, N. R. Chellew, V. G. Trice, Jr.

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 496-500

dx.doi.org/10.13182/NSE59-A15508

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. III. Preparation of Experimental Alloys

D. C. Hampson, G. A. Bennett, N. R. Chellew

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 501-503

dx.doi.org/10.13182/NSE59-A15509

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. IV. Interaction of Uranium and Its Alloys with Refractory Oxides

C. L. Rosen, N. R. Chellew, H. M. Feder

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 504-510

dx.doi.org/10.13182/NSE59-A15510

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. V. Yield of Fissionable Material upon Pouring

G. A. Bennett, N. R. Chellew, D. C. Hampson

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 511-513

dx.doi.org/10.13182/NSE59-A15511

An Iteration Method for the Specification of Multigroup Bucklings

A. Foderaro

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 514-524

dx.doi.org/10.13182/NSE59-A15512

The Shielding of Helical Ducts

C. C. Horton

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 525-529

dx.doi.org/10.13182/NSE59-A15513

Material Buckling Measurements in a Subcritical Assembly

Robert E. Uhrig

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 530-532

dx.doi.org/10.13182/NSE59-A15514

Low Decontamination Reprocessing of Thorium-Uranium Alloys by Induction Drip Melting

F. W. Dodge, E. W. Murbach, L. A. Hanson

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 533-536

dx.doi.org/10.13182/NSE59-A15515

Breeding Potential of Thermal Reactors

J. Chernick, S. Oleksa Moore

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 537-544

dx.doi.org/10.13182/NSE59-A15516

Interpretation of Thermal Neutron Mean Lifetime Experiments

Fred Holzer, Marshall F. Crouch

Nuclear Science and Engineering / Volume 6 / Number 6 / December 1959 / Pages 545-553

dx.doi.org/10.13182/NSE59-A15517