Home / Publications / Journals / Nuclear Science and Engineering / Volume 40 / Number 1

Volume 40

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