Home / Publications / Journals / Nuclear Science and Engineering / Volume 41 / Number 2

Volume 41

Number 2

Table of Contents
GSSLRN-I: An Automated Least-Squares Computer Code for the Analysis of Photopeak Spectra(G. D. Seybold)
RICE(J. D. Jenkins)
Cure for Chaos(Alvin M. Weinberg)
Heat Conduction in Reactor Fuel Elements(G. Hetsroni, E. Wacholder, S. Haber)
A Method of Correlation of Burnup Measurements for Physics Prediction of Fast Power Reactor Life(A. Gandini)

Primary-Recoil Atom Spectra from ENDF/B Data

J. D. Jenkins

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 155-163

Technical Paper / dx.doi.org/10.13182/NSE70-A20703

Neutron Spectrum Measurements in a Homogeneous Erbium System and Erbium Cross Sections

T. Gozani, G. D. Trimble

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 164-176

Technical Paper / dx.doi.org/10.13182/NSE70-A20704

Neutron Fission Cross Sections for ²³¹Th, ²³³Th, ²³⁵U, ²³⁷U, ²³⁹U, ²⁴¹Pu, and ²⁴³Pu from 0.5 to 2.25 MeV Using (t, pf) Reactions

J. D. Cramer, H. C. Britt

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 177-187

Technical Paper / dx.doi.org/10.13182/NSE70-A20705

Total Neutron Cross Section of Technetium-99 from 0.01 to 1000 eV

T. Watanabe, S. D. Reeder

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 188-192

Technical Paper / dx.doi.org/10.13182/NSE70-A20706

A Unified Model of Deformed Odd-Odd Nuclei for Nuclear Data Generation and Analysis

C. Y. Fu, K. J. Yost

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 193-208

Technical Paper / dx.doi.org/10.13182/NSE70-A20707

Reaction Rates in Representative Plutonium-Recycle Fuel Lattices

J. G. Carver, W. R. Morgan, C. R. Porter, M. A. Robkin

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 209-225

Technical Paper / dx.doi.org/10.13182/NSE70-A20708

Linearly Anisotropic Extensions of Asymptotic Neutron Diffusion Theory

R. J. Doyas, B. L. Koponen

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 226-236

Technical Paper / dx.doi.org/10.13182/NSE70-A20709

Truncation Error Analysis of Finite Difference Approximations to the Transport Equation

Wm. H. Reed, K. D. Lathrop

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 237-248

Technical Paper / dx.doi.org/10.13182/NSE70-A20710

Spectral Synthesis Applied to Fast-Reactor Dynamics

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 249-258

Technical Paper / dx.doi.org/10.13182/NSE70-A20711

Monte Carlo Method for Geometrical Perturbation and its Application to the Pulsed Fast Reactor

Hiroshi Takahashi

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 259-270

Technical Paper / dx.doi.org/10.13182/NSE70-A20712

Hybrid Computer Solution of Thermal Energy Equations in Porous Fuels

W. W. Marr, M. M. El-Wakil

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 271-280

Technical Paper / dx.doi.org/10.13182/NSE70-A20713

Transient Digital Control of a Boiling-Water Reactor Power Plant

W. Ciechanowicz, B. Lazarević

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 281-293

Technical Paper / dx.doi.org/10.13182/NSE70-A20714

An Experimental Investigation of Absorption in the 1.056 eV Resonance of Plutonium-240

Charles J. Hulka, Gene L. Woodruff

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 294-296

Technical Note / dx.doi.org/10.13182/NSE70-A20715

Use of Californium-252 as a Randomly Pulsed Neutron Source for Prompt Neutron Decay Measurements

John T. Mihalczo

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 296-298

Technical Note / dx.doi.org/10.13182/NSE70-A20716

Gozani's Pulsed Neutron Technique with Repeated Recycling of Analyzer Between Bursts

R. H. Chow

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 298-299

Technical Note / dx.doi.org/10.13182/NSE70-A20717

An Implicit Method for Solving the Lumped Parameter Reactor-Kinetics Equations by Repeated Extrapolation

Masayuki Izumi, Takashi Noda

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 299-303

Technical Note / dx.doi.org/10.13182/NSE70-A20718

Interface Conditions for Discontinuous Flux Synthesis Methods

William B. Terney

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 303-307

Technical Note / dx.doi.org/10.13182/NSE70-A20719

A Slow Neutron Scattering Routine from the Gas Model

John R. Eriksson

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 307-309

Technical Note / dx.doi.org/10.13182/NSE70-A20720

Geometric Interpretation of the Function g(c,µ) of Neutron Transport Theory

Perry A. Newman, Robert L. Bowden

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 309-310

Technical Note / dx.doi.org/10.13182/NSE70-A20721

Comparisons of Monte Carlo Calculations to Measurements of Neutron Leakage from the TSF-SNAP Reactor

V. R. Cain

Nuclear Science and Engineering / Volume 41 / Number 2 / August 1970 / Pages 310-315

Technical Note / dx.doi.org/10.13182/NSE70-A20722