ANS / Publications / Journals / Nuclear Science and Engineering

Transient Behavior of TRIGA, a Zirconium-Hydride, Water-Moderated Reactor

Richard Stone, H. P. Sleeper, J. R., Ralph, H. Stahl, Gordon West

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 255-259

Technical Paper / dx.doi.org/10.13182/NSE59-A28840

Polynomial Approximations in Neutron Transport Theory

W. R. Conkie

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 260-266

Technical Paper / dx.doi.org/10.13182/NSE59-A28841

An Iterative Method in Neutron Transport Theory

W. R. Conkie

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 267-271

Technical Paper / dx.doi.org/10.13182/NSE59-A28842

An Efficient Counting System for the Detection of Neutrons from Low-Yield Pulsed Neutron Sources

Lawrence Ruby, Joseph Bechen

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 272-278

Technical Paper / dx.doi.org/10.13182/NSE59-A28843

A Fuel Element for an Elevated-Temperature Critical Assembly

Carl E. Walter

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 279-283

Technical Paper / dx.doi.org/10.13182/NSE59-A28844

Errors in Reactivity Measurements Due to Photoneutron Effects

Charles Erwin Cohn

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 284-287

Technical Paper / dx.doi.org/10.13182/NSE59-A28845

A Monte Carlo Calculation of Thermal Utilization

A. Rotenberg, A. Lapidus, E. Wetherwell

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 288-293

Technical Paper / dx.doi.org/10.13182/NSE59-A28846

Flux Perturbation Produced by Ion Chambers and Fission Chambers

Alain Scola, William Managan

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 294-297

Technical Paper / dx.doi.org/10.13182/NSE59-A28847

Calculations of Flux Distributions in a Boiling Water Reactor

Y. Fukai, A. Shimizu, S. Miyamoto

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 298-305

Technical Paper / dx.doi.org/10.13182/NSE59-A28848

Flow Coastdown in a Loop After Pumping Power Cutoff

David Burgreen

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 306-312

Technical Paper / dx.doi.org/10.13182/NSE59-A28849

The Time-Dependent Thermal Neutron Flux from a Pulsed Subcritical Assembly

Stanley C. Fultz

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 313-319

Technical Paper / dx.doi.org/10.13182/NSE59-A28850

Kinetics of a Reactor Composed of Two Loosely Coupled Cores

G. C. Baldwin

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 320-327

Technical Paper / dx.doi.org/10.13182/NSE59-A28851

Measuring the Release Time and Total Drop Time of a Control Rod

Charles Zucker, Lewis Haring

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 328-332

Technical Paper / dx.doi.org/10.13182/NSE59-A28852

The Fluorination of Plutonium Tetrafluoride and Plutonium Dioxide by Fluorine

M. J. Steindler, D. V. Steidl, R. K. Steunenberg

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 333-340

Technical Paper / dx.doi.org/10.13182/NSE59-A28853

The Application of Topological Methods to the Kinetics of Homogeneous Reactors

Henri B. Smets, Elias P. Gyftopoulos

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 341-349

Technical Paper / dx.doi.org/10.13182/NSE59-A28854

On the Removal of Volatile Fission Products from Uranium-Bismuth Reactor Fuels

Orrington E. Dwyer, Allen M. Eshaya

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 350-360

Technical Paper / dx.doi.org/10.13182/NSE59-A28855