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

Volume 39

Number 1

Table of Contents
Comments on the Iterative Approach to a Space-Time Nonlinear Problem(H. Ibarra)
Reply to Comments on the Iterative Approach to a Space-Time Nonlinear Problem(Louis M. Shotkin)
Comments on Theoretical and Experimental Criteria for Reactor Stability(F. Di Pasquantemio, F. Kappel)
Comments on the Neutron Transport Theory with Anisotropic Scattering(K. O. Thielheim, K. Claussen)
WANSY(J. B. Yasinsky, J. W. Marinacci, A. V. Vota)
Advantages of Using a Combination Electromagnetic and Material Shield(R. D. SHELTON, H. E. STERN, J. W. WATTS)
Computer Code Abstract Citation(T. B. Fowler, D. R. Vondy)
Annual Review of Nuclear Science, Volume 18(Lothar W. Nordheim)
Engineering Compendium on Radiation Shielding, Vol. 1: Shielding Fundamentals, and Methods(Herbert Goldstein)

A Generalization of the Finite Difference Approximation Method with an Application to Space-Time Nuclear Reactor Kinetics

Raymond E. Alcouffe, Robert W. Albrecht

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 1-13

Technical Paper / dx.doi.org/10.13182/NSE70-A21166

Improvements in Fast Reactor Space-Energy Synthesis

R. J. Neuhold, K. O. Ott

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 14-24

Technical Paper / dx.doi.org/10.13182/NSE70-A21167

Doppler Broadening in a Medium with Both Temperature and Boundary Motion

S. T. Perkins

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 25-31

Technical Paper / dx.doi.org/10.13182/NSE70-A21168

Doppler Effect Studies Using Multilevel Formalism

R. N. Hwang

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 32-49

Technical Paper / dx.doi.org/10.13182/NSE70-A21169

Determination of Fission Density in ²³⁵U and Implications from Its Mass Distribution

Petru Popa, Marcel De Coster, Pieter H. M. Van Assche

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 50-55

Technical Paper / dx.doi.org/10.13182/NSE70-A21170

The Influence of a Reentrant Hole on Measurements of Fast and Thermal Neutron Spectra

Frank McGirt, Martin Becker

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 56-66

Technical Paper / dx.doi.org/10.13182/NSE70-A21171

Fast Neutron Cross Sections of Hafnium, Gadolinium, and Samarium

G. L. Sherwood, A. B. Smith, J. F. Whalen

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 67-80

Technical Paper / dx.doi.org/10.13182/NSE70-A21172

Gamma-Ray Spectra of the Products of Thermal-Neutron Fission of ²³⁵U at Selected Times after Fission

L. R. Bunney, D. Sam

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 81-91

Technical Paper / dx.doi.org/10.13182/NSE70-A21173

Theoretical Dose Transmission and Reflection Probabilities for 0.2-10.0 MeV Photons Obliquely Incident on Finite Concrete Barriers

W. O. Doggett, Fred A. Bryan, Jr.

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 92-104

Technical Paper / dx.doi.org/10.13182/NSE70-1

Construction of Lyapunov Functions for Nonlinear Reactor Stability Studies

M. A. Pai, V. R. Sastry, M. Ananda Mohan

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 105-107

Technical Note / dx.doi.org/10.13182/NSE70-A21175

Comparison of Methods for Determining Moderator Level Reactivity Coefficients

S. E. Wennemo-Hanssen

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 107-109

Technical Note / dx.doi.org/10.13182/NSE70-A21176

Control Rod Programming Optimization Using Dynamic Programming

William B. Terney, Henri Fenech

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 109-114

Technical Note / dx.doi.org/10.13182/NSE70-A21177

A Theory of Control-Rod Programming Optimization in Two-Region Reactors

Hiroshi Motoda, Toshio Kawai

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 114-118

Technical Note / dx.doi.org/10.13182/NSE70-A21178

Surface Multiplication

R. E. Wilson, R. J. Hall, E. D. Clayton

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 119-120

Technical Note / dx.doi.org/10.13182/NSE70-A21179

The Influence of the Density Effect on Electron-Induced Cascade Showers in Water and Aluminum

Harold L. Beck

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 120-121

Technical Note / dx.doi.org/10.13182/NSE70-A21180

Effective Equally Limiting Hot Channels in Reactor Thermal Design

A. Amendola

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 121-123

Technical Note / dx.doi.org/10.13182/NSE70-A21181

The Effect of Stored Energy on Measurements of Thermal Diffusivity During Irradiation

R. M. Carroll, R. B. Perez, O. Sisman

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 123-126

Technical Note / dx.doi.org/10.13182/NSE70-A21182

Radiation Heat Transfer in Ceramic Oxide Fuel Elements

J. A. Stoddard, N. J. McCormick

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 126-129

Technical Note / dx.doi.org/10.13182/NSE70-A21183

Number 2

Table of Contents

Slug-Flow Nusselt Numbers for In-Line Flow Through Unbaffled Rod Bundles

O. E. Dwyer, H. C. Berry

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 143-150

Technical Paper / dx.doi.org/10.13182/NSE70-A21194

A Variational Approach for the Determination of Neutron Flux Spectra from Detector Activation

R. W. Brandon, J. C. Robinson, C. W. Craven, Jr.

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 151-162

Technical Paper / dx.doi.org/10.13182/NSE70-A21195

Delayed Neutrons from Low Energy Photofission

L. A. Kull, R. L. Bramblett, T. Gozani, D. E. Rundquist

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 163-169

Technical Paper / dx.doi.org/10.13182/NSE70-A21196

Neutron Wave Analysis in Finite Media

K. Nishina, A. Z. Akcasu

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 170-181

Technical Paper / dx.doi.org/10.13182/NSE70-A21197

Neutron Pulse Propagation in a Multiplying Medium

P. K. Doshi, George H. Miley

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 182-192

Technical Paper / dx.doi.org/10.13182/NSE70-A21198

A Study of the Pulsed Neutron Problem in Ice in the Temperature Range 273 to 21°K

S. P. Tewari, L. S. Kothari

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 193-206

Technical Paper / dx.doi.org/10.13182/NSE70-A21199

An Adjoint-Weighting in Neutron Fluctuation Analysis with Emphasis on an Effective Detector Efficiency

M. E. Congdon, R. W. Albrecht

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 207-214

Technical Paper / dx.doi.org/10.13182/NSE70-A21200

Analysis of a Radially Loaded Thermal Reactor

J. C. Vigil, R. J. LaBauve, J. L. Meem

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 215-225

Technical Paper / dx.doi.org/10.13182/NSE70-A21201

Application of Variational Synthesis to the Optimal Control of Spatially Dependent Reactor Models

W. M. Stacey, Jr.

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 226-230

Technical Paper / dx.doi.org/10.13182/NSE70-A21202

Digital Control of the Halden Boiling Water Reactor by a Concept Based on Modern Control Theory

T. J. Bjørlo, R. Grumbach, R. Josefsson, K. O. Solberg

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 231-240

Technical Paper / dx.doi.org/10.13182/NSE70-A21203

On the Use of Point Kinetics for the Analysis of Rod-Ejection Accidents

J. B. Yasinsky

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 241-256

Technical Paper / dx.doi.org/10.13182/NSE70-A21204

The Beta-Decay Half-Life of ²⁴¹Pu

Robert G. Nisle, Ivan E. Stepan

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 257-258

Technical Note / dx.doi.org/10.13182/NSE70-A21205

Self-Absorption of Monoenergetic Electrons in Cobalt Foils

William H. Roach

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 258-259

Technical Note / dx.doi.org/10.13182/NSE70-A21206

Analysis of the Transmission of 24 keV Neutrons by Gold Spheres Using Spin-Dependent S-Wave Statistics

Thor T. Semler

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 259-263

Technical Note / dx.doi.org/10.13182/NSE70-A21207

Integral Tests of ENDF/B and GAM Neutron Cross-Section Data in a Clean Fast Assembly

R. A. Moore, D. A. Sargis, S. C. Cohen

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 263-272

Technical Note / dx.doi.org/10.13182/NSE70-A21208

Polywater as the Mechanism for the pH-Reactivity Effect in Pressurized Water Reactors

Walter H. D'Ardenne

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 272-273

Technical Note / dx.doi.org/10.13182/NSE70-A21209

Transient Solutions of the Neutron Slowing Down Equation

T. J. Williamson

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 273-277

Technical Note / dx.doi.org/10.13182/NSE70-A21210

A Variational Rebalancing Method for Linear Iterative Convergence Schemes of Neutron Diffusion and Transport Equations

Shoichiro Nakamura

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 278-283

Technical Note / dx.doi.org/10.13182/NSE70-A21211

On the Validity of Some Approximate Zero-Power Describing Functions

J. K. Vaurio, G. Pulkkis

Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 283-285

Technical Note / dx.doi.org/10.13182/NSE70-A21212

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