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Volume 11

Number 4

Table of Contents
Additional Exponential Representations of Gamma-Ray Build-Up Factors(G. L. STROBEL)
Re: “Thermal Neutron Flux Depression by Absorbing Foils” and “Flux Perturbations by Thermal Neutron Detectors”(R. H. RITCHIE, G. R. DALTON)
The Milne Problem with a Polynomial Source(T. AUERBACH)

The Thermal Utilization in a Rectangular Cell

A. PAZY, S. GOSHEN

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 357-361

Technical Paper / dx.doi.org/10.13182/NSE61-A26036

Gamma Ray Streaming Through Two-Legged Rectangular Ducts

J. C. LEDOUX, A. B. CHILTON

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 362-368

Technical Paper / dx.doi.org/10.13182/NSE61-A26037

Low Energy Neutron Cross Sections of Dy¹⁶⁴

R. SHER, S. TASSAN, E. V. WEINSTOCK, A. HELLSTEN

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 369-376

Technical Paper / dx.doi.org/10.13182/NSE61-A26038

FUELCYC, a New Computer Code for Fuel Cycle Analysis: Part I. Computational Model

RAYMOND T. SHANSTROM, MANSON BENEDICT

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 377-385

Technical Paper / dx.doi.org/10.13182/NSE61-A26039

FUELCYC, a New Computer Code for Fuel Cycle Analysis: Part II. Examples of Applications

MANSON BENEDICT, RAYMOND T. SHANSTROM, STANLEY L. AMBERG, N. BARRIE MCLEOD, PAUL T. STERANKA

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 386-396

Technical Paper / dx.doi.org/10.13182/NSE61-A26040

Measurement of ν in Fast Neutron Fission of Th²³² and U²³⁸

H. CONDÉ, N. STARFELT

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 397-404

Technical Paper / dx.doi.org/10.13182/NSE61-A26041

The Determination of the Period-Reactivity Relation and Open-Loop Reactor Transfer Function From Rod-Drop Decay Data

W. J. FADER, R. C. HARRISON

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 405-414

Technical Paper / dx.doi.org/10.13182/NSE61-A26042

Neutron Transport with Anisotropic Scattering

Janusz R. Mika

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 415-427

Technical Paper / dx.doi.org/10.13182/NSE61-1

On the Stability of Homogeneous Nuclear Reactors with Non-Linear Reactivity Dependence on Temperature

HENRI B. SMETS

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 428-433

Technical Paper / dx.doi.org/10.13182/NSE61-A26044

Preparation and Fabrication of Plutonium Fuel Alloy for Los Alamos Molten Plutonium Reactor Experiment No.1

J. W. ANDERSON, W. D. MCNEESE, C. C. BURWELL, J. A. LEARY

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 434-440

Technical Paper / dx.doi.org/10.13182/NSE61-A26045

A Discussion of the Correlation of Critical Conditions for Bare Homogeneous Reactors

BENJAMIN PINKEL, GEORGE B. W. YOUNG

Nuclear Science and Engineering / Volume 11 / Number 4 / December 1961 / Pages 441-449

Technical Paper / dx.doi.org/10.13182/NSE61-A26046

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