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Volume 49

Number 3

Tritium Generation in the Coolant-Moderator of Pressurized Water Reactors

Karl Hornyik

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 247-254

Technical Paper / dx.doi.org/10.13182/NSE72-A22539

Optimum Binary Signals for Reactor Frequency Response Measurements

M. R. Buckner, T. W. Kerlin

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 255-262

Technical Paper / dx.doi.org/10.13182/NSE72-A22540

Minimum Critical Mass in Intermediate Reactors Subject to Constraints on Power Density and Fuel Enrichment

P. Goldschmidt

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 263-273

Technical Paper / dx.doi.org/10.13182/NSE72-A22541

Critical Experiments for the Brookhaven Pulsed Fast Reactor Study

J. Phelps, H. Windsor, H. Takahashi, J. Conant, K. Chandramoleswar

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 274-300

Technical Paper / dx.doi.org/10.13182/NSE72-A22542

The Angular Distribution of Thermal Neutrons at the Surfaces of Black and Grey Cylinders

D. G. Doutriaux, D. G. Andrews

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 301-309

Technical Paper / dx.doi.org/10.13182/NSE72-A22543

The Ratio of the Uranium-238 to Uranium-235 Fission Cross Sections from 1 to 5 MeV

J. W. Meadows

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 310-316

Technical Paper / dx.doi.org/10.13182/NSE72-A22544

Neutron Capture Cross Sections in the keV Region for 154Sm, 160Gd, 164Dy, and 165Ho

L. R. Fawcett, Jr., A. Keith Furr, J. G. Lindsay

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 317-329

Technical Paper / dx.doi.org/10.13182/NSE72-A22545

Measurement and Analysis of Fast Neutron Spectra in Uranium Depleted in the Uranium-235 Isotope

N. N. Kaushal, B. K. Malaviya, M. Becker, E.T. Burns, E. R. Gaerttner

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 330-348

Technical Paper / dx.doi.org/10.13182/NSE72-A22546

Evaluation of Gamma-Ray Shielding Calculations and Determination of Shielding Parameters with Bremsstrahlung Radiation

L. F. Rodriguez, A. Shapiro

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 349-357

Technical Paper / dx.doi.org/10.13182/NSE72-A22547

Measurement of the Ratio of the Prompt to the Delayed Neutronic Response of a Self-Powered Vanadium Detector by Cross-Correlation Techniques

W. Seifritz

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 358-369

Technical Paper / dx.doi.org/10.13182/NSE72-A22548

The Integral Transform Method for the Average Neutron Transport Properties of a Lattice

M. opi

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 370-376

Technical Note / dx.doi.org/10.13182/NSE72-A22549

Analytical Treatment of Neutron Age in Perpendicular Direction in Slab Lattices

Kalimullah, K. S. Ram, G. Srikantiah

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 376-384

Technical Note / dx.doi.org/10.13182/NSE72-A22550

The Treatment of Boundary Value Problems in Optically Thick Media by Means of Lie Series

T. Auerbach, W. Hälg, J. Mennig

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 384-387

Technical Note / dx.doi.org/10.13182/NSE72-A22551

Calculations of Cadmium Cutoff Energies

Antanasije Koci

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 387-389

Technical Note / dx.doi.org/10.13182/NSE72-A22552

Note on the Fast Neutron Cross Sections of Palladium

A. B. Smith, P. Lambropoulos, P. Guenther, J. Whalen

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 389-392

Technical Note / dx.doi.org/10.13182/NSE72-A22553

Total Neutron Cross Section of Mylar at Low Energies

C. Castro Madero, F. Kropff, A. Oliva, J. M. Neill

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 392-393

Technical Note / dx.doi.org/10.13182/NSE72-A22554

Specification and Testing of Nuclear Data Required for Monte Carlo Transport Calculations

E. D. Cashwell, E. F. Plechaty

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 394-395

Technical Note / dx.doi.org/10.13182/NSE72-A22555

The Validity of Using Only Primary Protons in Van Allen Belt and Solar-Flare Proton Shielding Studies

R. T. Santoro, R. G. Alsmiller, Jr., J. Barish

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 395-398

Technical Note / dx.doi.org/10.13182/NSE72-A22556

Laminar- and Slug-Flow Heat Transfer Characteristics of Fuel Rods Adjacent to Fuel Subassembly Walls

Chia-Jung Hsu

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 398-404

Technical Note / dx.doi.org/10.13182/NSE72-A22557