Home / Publications / Journals / Nuclear Science and Engineering / Volume 40

Volume 40

Number 1 | Number 2 | Number 3

Number 1

Table of Contents
On Comparison of Synthetic Kernel Transport Results(M. Natelson)
PARTI(A. A. Harms, J. A. Stoddard)
XSDRN: A Discrete Ordinates Spectral Averaging Code(N. M. Greene, C. W. Craven, Jr.)
Reactor-Noise Analysis in the Time Domain(J. D. Orndoff)
Introduction to Modern Physics(G. W. Spangler)

Deposition of Particles in Turbulent Flow on Channel or Pipe Walls

S. K. Beal

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE70-A18874

The Thermal-Neutron-Absorption Cross Sections of ⁶Li and ¹⁰B

J. W. Meadows, J. F. Whalen

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 12-16

Technical Paper / dx.doi.org/10.13182/NSE70-A18875

Approximate Dispersion Relations and the Total Coherent Inelastic Neutron Scattering Cross Section for Graphite

Robert Conn

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 17-24

Technical Paper / dx.doi.org/10.13182/NSE70-A18876

The Construction of Neutron Cross Sections in the Unresolved Resonance Region

Yukio Ishiguro, Satoru Katsuragi, Masayuki Nakagawa, Hideki Takano

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 25-37

Technical Paper / dx.doi.org/10.13182/NSE70-A18877

The Linear Vector Space Theory of Unfolding

N. Karayianis, C. A. Morrison, D. E. Wortman

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 38-50

Technical Paper / dx.doi.org/10.13182/NSE70-A18878

Evaluation of Neutron Spectral Effects in Systems with Thermal Resonance Absorbers by Applying a Correlation Method to Measured Spectral Indexes

A. Gibello, F. V. Orestano, F. Pistella, E. Santandrea

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 51-72

Technical Paper / dx.doi.org/10.13182/NSE70-A18879

General Multigroup and Spectral Synthesis Equations

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 73-90

Technical Paper / dx.doi.org/10.13182/NSE70-A18880

Numerical Solution of the Time- and Space-Dependent Multigroup Neutron Diffusion Equations

W. R. Rhyne, A. C. Lapsley

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 91-100

Technical Paper / dx.doi.org/10.13182/NSE70-A18881

A Study of Physics Parameters in Several H₂O-Moderated Lattices of Slightly Enriched and Natural Uranium

J. Hardy, Jr., D. Klein, J. J. Volpe

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 101-115

Technical Paper / dx.doi.org/10.13182/NSE70-A18882

A Comparison of Thermal-Neutron-Activation Measurements and Monte Carlo Calculations in Light-Water-Moderated Uranium Cells

J. J. Volpe, J. Hardy, Jr., D. Klein

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 116-127

Technical Paper / dx.doi.org/10.13182/NSE70-A18883

Buildup Factors in Water for Gamma Rays of 1 MeV and Lower Energy

E. E. Morris, A. B. Chilton

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 128-129

Technical Note / dx.doi.org/10.13182/NSE70-A18884

Reduction of the Residual Photon Dose Rate Around High-Energy Proton Accelerators

T. W. Armstrong, J. Barish

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 129-132

Technical Note / dx.doi.org/10.13182/NSE70-A18885

Null-Reactivity Measurements of Capture/Fission Ratio in ²³⁵U and ²³⁹Pu

C. E. Till, J. M. Gasidlo, E. F. Groh, L. G. LeSage, W. R. Robinson, G. S. Stanford

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 132-136

Technical Note / dx.doi.org/10.13182/NSE70-A18886

Cross Section for the Delayed-Neutron Yield from the ¹⁷O(n,p)¹⁷N Reaction at 14.1 MeV

H. O. Menlove, R. H. Augustson, C. N. Henry

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 136-138

Technical Note / dx.doi.org/10.13182/NSE70-A18887

Heterogeneity Effects on Neutron Self-Shielding Factors for Fast Reactors

G. Bitelli, M. Salvatores, G. Cecchini

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 138-140

Technical Note / dx.doi.org/10.13182/NSE70-A18888

On the Effect of Delayed Neutrons in Reactor Excursions with Ramp Reactivity Insertion

David L. Hetrick, José Canosa

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Page 141

Technical Note / dx.doi.org/10.13182/NSE70-A18889

Pulse Characteristics for Ramp Reactivity Insertion and Energy-Shutdown Reactor Excursions

R. F. Redmond

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 141-144

Technical Note / dx.doi.org/10.13182/NSE70-A18890

Reactivity Changes Due to the Random Vibration of Control Rods and Fuel Elements

M. M. R. Williams

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 144-150

Technical Note / dx.doi.org/10.13182/NSE70-A18891

Qualitative Evaluation of Fast Reactor Melt-Down Accidents

Masaoki Komata

Nuclear Science and Engineering / Volume 40 / Number 1 / April 1970 / Pages 150-152

Technical Note / dx.doi.org/10.13182/NSE70-A18892

Number 2

Table of Contents
3DB: A Three-Dimensional Diffusion Theory Burnup Code(R. W. Hardie, W. W. Little, Jr)
FARED(D. H. Roy, J. M. Tilford)
REPCDC(W. Rothenstein)
LAPH(Donald J. Dudziak, Alan H. Marshall, Robert E. Seaman)
REFLOS(W. Boettcher, E. Schmidt)
Nuclear Structure(Lothar W. Nordheim)
Fundamentals of Radiation Protection(Herbert M. Parker)
Economic Strategy for Developing Breeder Reactors(James A. Lane, L. Duane Chapman)
The Art of Computer Programming(G. E. Whitesides)
Formal Languages and their Relation to Automata(James B. Morris)
Information Retrieval Systems Characteristics, Testing, and Evaluation(Margaret K. Butler)
Induced Radioactivity(S. A. Reynolds)
On the Calculation of Neutron Lifetimes(Jeffery Lewins)
Comparison of Modal and Iterative Approaches to Space and Space-Time Nonlinear Problems(Louis M. Shotkin)
Corrigenda(Z. M. Bartolome, R. W. Hockenbury, W. R. Moyer, J. R. Tatarczuk, R. C. Block)

The Statistical Uncertainty in Doppler Coefficient Calculations for Fast Reactors

C. R. Adkins, M. W. Dyos

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 159-172

Technical Paper / dx.doi.org/10.13182/NSE70-A19680

Measurements and Detailed Model Analysis of Space-Correlated Reactor Fluctuations

D. R. Harris, M. Natelson, J. A. Galey, E. Schmidt

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 173-198

Technical Paper / dx.doi.org/10.13182/NSE70-A19681

Estimation of the Dynamic Reactivity Using Digital Kalman Filtering

Joseph C. Venerus, Thomas E. Bullock

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 199-205

Technical Paper / dx.doi.org/10.13182/NSE70-A19682

Weighted-Residual Methods in Space-Dependent Reactor Dynamics

E. L. Fuller, D. A. Meneley, D. L. Hetrick

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 206-223

Technical Paper / dx.doi.org/10.13182/NSE70-A19683

The Integral Transform Method for Neutron Transport Problems

H. Hembd

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 224-238

Technical Paper / dx.doi.org/10.13182/NSE70-A19684

Point Source Green's Functions for Neutral Particle Transport

James F. Meyer, Alan M. Jacobs

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 239-245

Technical Paper / dx.doi.org/10.13182/NSE70-A19685

Study of the Use of Pulsed-Neutron Experiments on Multiplying Lattices for the Adjustment of Criticality Codes

V. Deniz

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 246-253

Technical Paper / dx.doi.org/10.13182/NSE70-A19686

Calculation of the Neutron Spectra from Proton-Nucleus Nonelastic Collisions in the Energy Range 15 to 18 MeV and Comparison with Experiment

R. G. Alsmiller, Jr., O. W. Hermann

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 254-261

Technical Paper / dx.doi.org/10.13182/NSE70-A19687

Predictions for Neutron Transport in Air, Based on Integral Measurements in Nitrogen and Oxygen at 14 MeV

L. F. Hansen, J. D. Anderson, E. Goldberg, J. Kammerdiener, E. Plechaty, C. Wong

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 262-282

Technical Paper / dx.doi.org/10.13182/NSE70-A19688

The ¹⁶⁰(n,xγ) Reaction for 67 ≤ E_n ≤ 11 MeV

J. K. Dickens, F. G. Perey

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 283-293

Technical Paper / dx.doi.org/10.13182/NSE70-A19689

Gamma-Ray-Production Cross Sections for Fast Neutron Interactions with Several Elements

Darrell M. Drake, John C. Hopkins, C. S. Young, H. Condé

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 294-305

Technical Paper / dx.doi.org/10.13182/NSE70-A19690

Measurements of the Neutron Fission and Absorption Cross Sections of ²³⁹Pu Over the Energy Region 0.02 eV to 30 keV

R. Gwin, L. W. Weston, G. de Saussure, R. W. Ingle, J. H. Todd, F. E. Gillespie, R. W. Hockenbury, R. C. Block

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 306-316

Technical Paper / dx.doi.org/10.13182/NSE70-A19691

Effects of Cladding Thickness and Thermal Conductivity on Heat Transfer to Liquid Metals Flowing In-Line Through Bundles of Closely Spaced Reactor Fuel Rods

O. E. Dwyer, H. C. Berry

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 317-330

Technical Paper / dx.doi.org/10.13182/NSE70-A19692

Threshold Reaction Excitation Functions Intercalibrated in a Pure Fission Spectrum

A.M. Bresesti, M. Bresesti, A. Rota, R. A. Rydin, L. Lesca

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 331-338

Technical Note / dx.doi.org/10.13182/NSE70-A19693

A Multigroup Two-Point Kinetic Model for the Time-Dependent Analysis of Two-Zone Fast Neutron Systems

P. d'Oultremont, J. C. Young

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 338-342

Technical Note / dx.doi.org/10.13182/NSE70-A19694

Multilevel Parameters for the ²³⁹Pu Fission Cross Section from 40 to 100 eV

P. Lambropoulos

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 342-346

Technical Note / dx.doi.org/10.13182/NSE70-A19695

The ¹⁴N(n,xγ) Reaction for 8.5 ≤ E_n ≤ 11 MeV

J. K. Dickens, F. G. Perey

Nuclear Science and Engineering / Volume 40 / Number 2 / May 1970 / Pages 346-348

Technical Note / dx.doi.org/10.13182/NSE70-A19696

Number 3

The Energy Distribution of Photoneutrons Produced by 150-MeV Electrons in Thick Beryllium and Tantalum Targets

R. G. Alsmiller, Jr., T. A. Gabriel, M. P. Guthrie

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 365-374

Technical Paper / dx.doi.org/10.13182/NSE70-A20187

A Measurement of the Fission Cross Sections of ²³⁹Pu and ²³³U Relative to ²³⁵U

E. Pfletschinger, F. Käppeler

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 375-382

Technical Paper / dx.doi.org/10.13182/NSE70-A20188

Measurement of the Ratios of Capture and Fission Neutron Cross Sections of ²³⁵U, ²³⁸U, and ²³⁹Pu at 130 to 1400 keV

W. P. Poenitz

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 383-388

Technical Paper / dx.doi.org/10.13182/NSE70-A20189

Total Neutron Cross Section of ²⁴²Pu

T. E. Young, S. D. Reeder

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 389-395

Technical Paper / dx.doi.org/10.13182/NSE70-A20190

Calculated ⁵⁶Fe Neutron Elastic and Inelastic Scattering and Gamma-Ray-Production Cross Sections from 1.0 to 7.6 MeV

W. E. Kinney, F. G. Perey

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 396-406

Technical Paper / dx.doi.org/10.13182/NSE70-A20191

Critical Parameters of a Uranium Solution Slab-Cylinder System

Grover Tuck, Harold E. Clark

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 407-413

Technical Paper / dx.doi.org/10.13182/NSE70-A20192

Analysis of Central Reactivity Worths in Fast Critical Assemblies

R. A. Karam, K. D. Dance, T. Nakamura, J. E. Marshall

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 414-423

Technical Paper / dx.doi.org/10.13182/NSE70-A20193

An Approximate Solution to the Asymptotic Slowing Down Equations of Fast Neutrons

M. Segev

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 424-437

Technical Paper / dx.doi.org/10.13182/NSE70-A20194

Some Monte Carlo Techniques for the Calculation of Doppler Coefficients

L. B. Miller, G. H. Miley

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 438-448

Technical Paper / dx.doi.org/10.13182/NSE70-A20195

Verification of Space-Time Reactor-Kinetics Analysis by Experiments

H. H. Hassan, G. H. Miley

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 449-459

Technical Paper / dx.doi.org/10.13182/NSE70-A20196

Space- and Time-Dependent Neutron Slowing Down

David J. Diamond, Sidney Yip

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 460-471

Technical Paper / dx.doi.org/10.13182/NSE70-A20197

Effect of Neutron Anisotropy on the Depletion of a Cylindrical Burnable Poison Pin

M. G. Zaalouk, J. O. Berg

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 472-477

Technical Paper / dx.doi.org/10.13182/NSE70-A20198

Use of Gauss-Laguerre Numerical Integration for Point Kernel Shielding Calculations

P. C. Cochrane, D. W. Mesh

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 478-483

Technical Note / dx.doi.org/10.13182/NSE70-A20199

Calculation of the Energy Deposited in Thick Targets by High-Energy (1 GeV) Electron-Photon Cascades and Comparison with Experiment—II

R. G. Alsmiller, Jr., H. S. Moran

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 483-485

Technical Note / dx.doi.org/10.13182/NSE70-A20200

Prompt Gamma Rays from Thermal Neutron Fission of Uranium-235

R. W. Peelle, F. C. Maienschein

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 485-486

Technical Note / dx.doi.org/10.13182/NSE70-A20201

Photon Cross Sections of Uranium and Plutonium

H. F. Atwater

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 487-488

Technical Note / dx.doi.org/10.13182/NSE70-A20202

A Numerical Calculation of the Time-Dependent Neutron Spectra in a Pulsed Homogeneous Multiplying System

Pablo Rodriguez, Dong H. Nguyen

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 488-491

Technical Note / dx.doi.org/10.13182/NSE70-A20203

Several Particular Solutions of the One-Speed Transport Equation

M. N. Özişik, C. E. Siewert

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 491-494

Technical Note / dx.doi.org/10.13182/NSE70-A20204

Prompt-Jump Correction of Inverse Kinetics Rod-Drop Measurements

Günter Kussmaul

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 494-498

Technical Note / dx.doi.org/10.13182/NSE70-A20205

Approximate Calculation of Prompt-Critical Excursions

Rubin Goldstein, Louis M. Shotkin

Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 498-500

Technical Note / dx.doi.org/10.13182/NSE70-A20206