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Volume 29

Number 2

Vaporization of Fission Products from Irradiated Fuels—I. Experimental Method and General Fission-Product Behavior

A. W. Castleman, Jr., I. N. Tang

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 159-164

Technical Paper / dx.doi.org/10.13182/NSE67-A18523

Correlation of Radiation Damage to Steel with Neutron Spectrum

W.F. Sheely

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 165-175

Technical Paper / dx.doi.org/10.13182/NSE67-A18524

Buffering of Uranium Monocarbide to Control Carbon Activity

W. Chubb

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 176-179

Technical Paper / dx.doi.org/10.13182/NSE67-A18525

An Intrinsic Method for Determining Absolute Thermal Flux and Power in Heterogeneous Reactors

G. E. Goring

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 180-188

Technical Paper / dx.doi.org/10.13182/NSE67-A18526

Secondary-Dose Equivalent Model and Comparison of 160-MeV Proton-Induced Neutron and Proton Dose with a Comprehensive Experiment

Bobby Liley, Arthur G. Duneer, Jr.

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 189-197

Technical Paper / dx.doi.org/10.13182/NSE67-A18527

Spatial Dependence of Slowing Down Times for 14.1-MeV Neutrons in Water

Shee-Ming Chen, Leon J. Lidofsky

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 198-209

Technical Paper / dx.doi.org/10.13182/NSE67-A18528

Charged Particle Slowing Down Spectra and Energy-Loss Distribution Resulting from Fast-Neutron Irradiation of Water

Richard E. Faw

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 210-217

Technical Paper / dx.doi.org/10.13182/NSE67-A18529

Capture Cross Sections of Neptunium-237

Donald C. Stupegia, Marcia Schmidt, Curtis R. Keedy

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 218-219

Technical Paper / dx.doi.org/10.13182/NSE67-A18530

A Derivation of Variational Principles for Inhomogeneous Equations

G. C. Pomraning

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 220-236

Technical Paper / dx.doi.org/10.13182/NSE67-A18531

Singular Difference Approximations for the Discrete Ordinate Equations in x-y Geometry

J. A. Davis, L. A. Hageman, R. B. Kellogg

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 237-243

Technical Paper / dx.doi.org/10.13182/NSE67-A18532

Concerning Infinitely Dilute Resonance Integrals

Coleridge A. Wilkins, Donald G. Thompson

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 244-247

Technical Paper / dx.doi.org/10.13182/NSE67-A18533

One-Speed Neutron Transport in Slab Geometry

S. Pahor

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 248-253

Technical Paper / dx.doi.org/10.13182/NSE67-A18534

Spectrum and Importance Function in Spatially Independent Fast-Reactor Assemblies

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 254-263

Technical Paper / dx.doi.org/10.13182/NSE67-A18535

State Variable Feedback Control of Multiregion Reactors

Lynn E. Weaver, Robert E. Vanasse

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 264-271

Technical Paper / dx.doi.org/10.13182/NSE67-A18536

A Procedure for Evaluating Modified Pulsed-Neutron- Source Experiments in Subcritical Nuclear Reactors

Christopher F. Masters, K. B. Cady

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 272-282

Technical Paper / dx.doi.org/10.13182/NSE67-3

Interpretation of Pulsed-Source Experiments in the Peach Bottom HTGR

C. A. Preskitt, E. A. Nephew, J. R. Brown, K. R. Van Howe

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 283-295

Technical Paper / dx.doi.org/10.13182/NSE67-4

Buckling Measurements in Water-Moderated and -Reflected Exponential Experiments

Henry H. Windsor

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 296-298

Technical Note / dx.doi.org/10.13182/NSE67-A18539

The Mismatch of Thermal and Epithermal Neutron Flux

K. B. Cady, G. J. Kirouac, J. J. McInerney

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 299-302

Technical Note / dx.doi.org/10.13182/NSE67-A18540

Solutions of the Time-Dependent One-Group Diffusion Equations for Reflected Systems

Rudolph Sher

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 302-305

Technical Note / dx.doi.org/10.13182/NSE67-A18541

The Extrapolated Endpoint for the Milne Problem

G. C. Pomraning, K. D. Lathrop

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 305-308

Technical Note / dx.doi.org/10.13182/NSE67-A18542

Subcritical Reactivity from Neutron Statistics

Arthur J. Lindeman, Lawrence Ruby

Nuclear Science and Engineering / Volume 29 / Number 2 / August 1967 / Pages 308-310

Technical Note / dx.doi.org/10.13182/NSE67-A18543