Home / Publications / Journals / Nuclear Science and Engineering / Volume 39 / Number 3

Volume 39

Number 3

Table of Contents
PHENIX: A Two-Dimensional Diffusion-Burnup-Refueling Code(R. Douglas O'Dell, Thomas J. Hirons)
The Space Dependence of Reactor Noise-II Calculations(James R. Sheff, Robert W. Albrecht)

Boundedness and Stability of Some Models of Nuclear Reactors

Henri B. Smets

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 289-295

Technical Paper / dx.doi.org/10.13182/NSE70-A19990

Coupled Sampling with the Monte Carlo Method in Neutron Transport Calculations

L. L. Carter, N. J. McCormick

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 296-310

Technical Paper / dx.doi.org/10.13182/NSE70-A19991

Minimum Critical Mass in Fast Reactors with Bounded Power Density

P. Goldschmidt, J. Quenon

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 311-319

Technical Paper / dx.doi.org/10.13182/NSE70-A19992

Critical Mass Irregularity of Steel-Moderated Enriched Uranium Metal Assemblies with Composite Steel-Oil Reflectors

Donald C. Coonfield, Grover Tuck, Harold E. Clark, Bruce B. Ernst

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 320-328

Technical Paper / dx.doi.org/10.13182/NSE70-A19993

Probability Distribution of Neutron Populations in a Multiplying Assembly

D. B. MacMillan

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 329-336

Technical Paper / dx.doi.org/10.13182/NSE70-A19994

An Analysis of the Neutron Capture Cross Section of ²³⁸U Between 1 keV and 15 MeV

W. G. Davey

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 337-360

Technical Paper / dx.doi.org/10.13182/NSE70-A19995

Fission Cross-Section Ratio Measurements of ²³⁹Pu and ²³³U to ²³⁵U from 0.24 to 24 keV

Wayne K. Lehto

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 361-367

Technical Paper / dx.doi.org/10.13182/NSE70-A19996

Low Flux Measurements of ²³⁹Pu and ²³⁵U Capture-to-Fission Ratios in a Fast Reactor Spectrum

M. M. Bretscher, W. C. Redman

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 368-378

Technical Paper / dx.doi.org/10.13182/NSE70-A19997

The Calculation of Gamma-Ray Transition Probabilities in Odd-A Nuclei

K. J. Yost, P. H. Pitkanen, C. Y. Fu

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 379-386

Technical Paper / dx.doi.org/10.13182/NSE70-A19998

Streamwise Heat Conduction Effects in Forced-Convection Boundary Layers Without and With Superposed Free Convection

E. M. Sparrow, R. P. Heinisch, H. S. Yu

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 387-393

Technical Paper / dx.doi.org/10.13182/NSE70-A19999

Fast-Reactor-Core Design Optimization by Linear Programming

Kotaro Inoue

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 394-398

Technical Note / dx.doi.org/10.13182/NSE70-A20000

Outer Iteration Scaling in Neutron Transport Codes

B. E. Clancy, I. J. Donnelly

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 398-400

Technical Note / dx.doi.org/10.13182/NSE70-A20001

Mullikin's Method for Solving the Neutron Thermalization Nonhomogeneous Equation

I. Caprini, A. Corciovei, V. Protopopescu

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 401-403

Technical Note / dx.doi.org/10.13182/NSE70-A20002

Extrapolation and Interpolation in Calculation of the Resonance Absorption of Neutrons of Intermediate Energy

Jörn Mikkelsen

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 403-407

Technical Note / dx.doi.org/10.13182/NSE70-A20003

A Method for Collapsing Fast-Reactor Neutron Cross Sections

M. Pavelescu, V. Anton, I. Purica

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 407-409

Technical Note / dx.doi.org/10.13182/NSE70-A20004

³He(n,p)T Cross Section from 0.3 to 1.16 MeV

D. G. Costello, S. J. Friesenhahn, W. M. Lopez

Nuclear Science and Engineering / Volume 39 / Number 3 / March 1970 / Pages 409-410

Technical Note / dx.doi.org/10.13182/NSE70-A20005