American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 30 / Number 3

Volume 30

Number 3

Thermoelastic Dynamics of a Pulse Reactor

David Burgreen

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 317-327

Technical Paper / dx.doi.org/10.13182/NSE67-A18395

The Use of Infinite Medium Spectra in Gamma-Ray Heating Calculations

T. E. Dudley, M. R. Mendelson, N. E. Holden

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 328-339

Technical Paper / dx.doi.org/10.13182/NSE67-A18396

Neutron Fluxes in Concrete Ducts Arising from Incident Epicadmium Neutrons: Calculations and Experiments

R. E. Maerker, F. J. Muckenthaler

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 340-354

Technical Paper / dx.doi.org/10.13182/NSE67-A18397

Neutron Total and Absorption Cross Sections of 238Pu

T. E. Young, F. B. Simpson, J. R. Berreth, M. S. Coops

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 355-361

Technical Paper / dx.doi.org/10.13182/NSE67-A18398

Decay of Thermalized Neutron Fields in Graphite

C. H. Reed, C. N. Henry, A. A. Usner

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 362-373

Technical Paper / dx.doi.org/10.13182/NSE67-A18399

Activation Measurement of the Doppler Effect for 238U Capture and 235U Fission in a Fast-Neutron Spectrum

G. R. Pflasterer, Jr., R. Sher

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 374-394

Technical Paper / dx.doi.org/10.13182/NSE67-A18400

Reactor Analysis by Monte Carlo

H. Rief, H. Kschwendt

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 395-418

Technical Paper / dx.doi.org/10.13182/NSE67-A18401

Application of the Natural Mode Approximation to Space-Time Reactor Problems

Larry R. Foulke, Elias P. Gyftopoulos

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 419-435

Technical Paper / dx.doi.org/10.13182/NSE67-A18402

Sinusoidal Analysis of a Low-Power Nuclear Reactor by the Wentzel-Kramers-Brillouin Approach

Sevim Tan

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 436-447

Technical Paper / dx.doi.org/10.13182/NSE67-A18403

Variational Functionals for Space-Time Neutronics

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 448-451

Technical Note / dx.doi.org/10.13182/NSE67-A18404

A Perturbation Method for Analysis of Neutron-Source-Worth Experiments in Nuclear Reactors

A. Gandini

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 451-453

Technical Note / dx.doi.org/10.13182/NSE67-A18405

Linear Analysis of Xenon Spatial Oscillations

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 453-455

Technical Note / dx.doi.org/10.13182/NSE67-A18406

Neutron Diffusion Using a Modulated Source

G. A. Massel, M. R. Feix

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 455-458

Technical Note / dx.doi.org/10.13182/NSE67-A18407

A Very Low-Temperature Nuclear Reactor

S. A. Dupree

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 458-461

Technical Note / dx.doi.org/10.13182/NSE67-A18408

Total Gamma Energy Release Due to Thermal-Neutron Fission in 235U

N. E. Holden, M. R. Mendelson, T. E. Dudley

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 461-463

Technical Note / dx.doi.org/10.13182/NSE67-A18409