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Volume 36

Number 2

Time-Energy-Dependent Neutron Transport in an Infinite Medium in the Framework of Age-Dependent Branching Processes

P. Wälti

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 133-142

Technical Paper / dx.doi.org/10.13182/NSE69-A19713

Experimental Neutron Kinetic Studies in a 238U Sphere

Tsahi Gozani

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 143-158

Technical Paper / dx.doi.org/10.13182/NSE69-A19714

The Loss-of-Coolant Accident Analysis in Pressurized Water Reactors

Amir N. Nahavandi

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 159-188

Technical Paper / dx.doi.org/10.13182/NSE69-A19715

A Unified Nuclear Model for the Generation of Nuclear Data

K. J. Yost, P. H. Pitkanen, C. Y. Fu

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 189-201

Technical Paper / dx.doi.org/10.13182/NSE69-A19716

The Measurement of Absolute Delayed-Neutron Yields from 3.1- and 14.9-MeV Fission

Christopher F. Masters, M. M. Thorpe, Darryl B. Smith

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 202-208

Technical Paper / dx.doi.org/10.13182/NSE69-A19717

An Accurate Determination of the Cadmium Ratio of Neutron Capture Rates in 238U in Slightly Enriched Uranium

Ç. Ertek, A. Yalçin, Y. İnel

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 209-219

Technical Paper / dx.doi.org/10.13182/NSE69-A19718

The Application of a Gamma-Ray Cascade Model to the Calculation of Neutron Energy-Dependent Capture Gamma-Ray Production Cross Sections

K. J. Yost, S. M. Kremer

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 220-231

Technical Paper / dx.doi.org/10.13182/NSE69-A19719

Measurements of Nonfission Heating in a High Neutron Flux Reactor

R. M. Carroll, R. B. Perez, O. Sisman

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 232-237

Technical Paper / dx.doi.org/10.13182/NSE69-A19720

Experimental Studies on Gamma-Ray Dose Rates from a 60Co Cylindrical Source with Shell-Shaped Shields

Yoshihiko Kanemori, Yutaka Furuta

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 238-245

Technical Paper / dx.doi.org/10.13182/NSE69-A19721

A Semiempirical Formula for Albedo of Alternating Layers

Takashi Nakamura, Tomonori Hyodo

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 246-250

Technical Paper / dx.doi.org/10.13182/NSE69-A19722

High-Energy (<400-MeV) Neutron Transport Using the Method of Discrete Ordinates

R. G. Alsmiller, Jr., F. R. Mynatt, J. Barish, W. W. Engle, Jr.

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 251-255

Technical Note / dx.doi.org/10.13182/NSE69-A19723