Home / Publications / Journals / Nuclear Science and Engineering / Volume 40 / Number 2

Volume 40

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