ANS / Publications / Journals / Nuclear Science and Engineering

Calculations of the Radiation Hazard Due to Exposure of Supersonic Aircraft to Solar-Flare Protons

M. Leimdorfer, R. G. Alsmiller, Jr., and R. T. Boughner

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 151-157

Technical Paper / dx.doi.org/10.13182/NSE67-A18259

High-Energy Nucleon Transport and Space Vehicle Shielding

R. G. Alsmiller, Jr.

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 158-189

Technical Paper / dx.doi.org/10.13182/NSE67-A18260

Electron Transport Theory, Calculations, and Experiments

C. D. Zerby and F. L. Keller

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 190-218

Technical Paper / dx.doi.org/10.13182/NSE67-A18261

Adjoint and Importance in Monte Carlo Application

R. R. Coveyou, V. R. Cain, and K. J. Yost

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 219-234

Technical Paper / dx.doi.org/10.13182/NSE67-A18262

Variance of Certain Flux Estimators Used in Monte Carlo Calculations

Francis H. Clark

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 235-239

Technical Paper / dx.doi.org/10.13182/NSE67-1

A Study of the Angular and Energy Distributions of Radiation at Small Distances from a Point Source of Gamma Rays or Neutrons

Charles Eisenhauer

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 240-251

Technical Paper / dx.doi.org/10.13182/NSE67-A18264

Doses Behind Vertical and Horizontal Barriers from a Plane Source of 1.25 MeV Gamma-Ray Photon

Dominic J. Raso and Stanley Woolf

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 252-264

Technical Paper / dx.doi.org/10.13182/NSE67-A18265

Deep Penetration of Radiation by the Method of Invariant Imbedding

D. R. Mathews, K. F. Hansen, and E. A. Mason

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 263-270

Technical Paper / dx.doi.org/10.13182/NSE67-A18266

One-Velocity Neutron Transport Problems by the Transfer Matrix Method

Raphael Aronson

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 271-282

Technical Paper / dx.doi.org/10.13182/NSE67-A18267

Measurements and Calculations of the Spectral and Spatial Details of the Fast-Neutron Flux in Water Shields

V. V. Verbinski, M. S. Bokhari, J. C. Courtney, and G. E. Whitesidestt

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 283-298

Technical Paper / dx.doi.org/10.13182/NSE67-A18268

Measurements of the Spectra of Uncollided Fission Neutrons Transmitted Through Thick Samples of Nitrogen, Oxygen, Carbon, and Lead: Investigation of the Minima in Total Cross Sections

C. E. Clifford, E. A. Straker, F. J. Muckenthaler, V. V. Verbinski, R. M. Freestone, Jr., K. M. Henry, and W. R. Burrus

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 299-307

Technical Paper / dx.doi.org/10.13182/NSE67-A18269

Neutron-Attenuation Experiments in Iron-Water Configurations

B. Chinaglia and D. Monti, C. Fedrighini and A. M. Moncassoli

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 308-317

Technical Paper / dx.doi.org/10.13182/NSE67-A18270

Experimental Differential Number, Energy and Exposure Albedos for Sem-finite Media, for Normally Incident Gamma Photons

J. J. Steyn, D. G. Andrews

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 318-327

Technical Paper / dx.doi.org/10.13182/NSE67-A18271

Capture and Fission Gamma-Ray Effective Spectra for Shielding

Donald J. Dudziak

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 328-337

Technical Paper / dx.doi.org/10.13182/NSE67-A18272

High-Energy Accelerator Shield-Leakage Neutron Spectra

Keran O'Brien, Robert Sanna, Mary Alberg, James E. McLaughlin, and Sam A. Rothenberg

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 338-347

Technical Paper / dx.doi.org/10.13182/NSE67-A18273

Neutron Exposure of the PM-2A Reactor Vessel

K. Shure and Carl T. Oberg

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 348-359

Technical Paper / dx.doi.org/10.13182/NSE67-A18274

An Analysis of a Shielding Experiment Performed in a Real Fallout Field

R. L. French, J. H. Price, and K. W. Tompkins

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 360-366

Technical Paper / dx.doi.org/10.13182/NSE67-A18275

Neutron Air-Transport Data for the Design of Protective Structures

R. H. Karcher

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 367-387

Technical Paper / dx.doi.org/10.13182/NSE67-A18276

Investigation of the Floor-Barrier Reduction Factor Used In Structure Shielding Theory

A. L. Kaplan

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 388-393

Technical Paper / dx.doi.org/10.13182/NSE67-A18277

Gamma-Ray Scattering Near an Air-Ground Interface

E. T. Clarke

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 394-402

Technical Paper / dx.doi.org/10.13182/NSE67-A18278

The Close-in Exposure Field From Point Isotropic Gamma-Ray Source Located at an Air-Ground Interface

A. B. Chilton

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 403-410

Technical Paper / dx.doi.org/10.13182/NSE67-A18279

Calculation of Doubly Differential Current Albedos for Epicadmium Neutrons Incident on Concrete and Comparison of the Reflected Subcadmium Component with Experiment

W. A. Coleman, R. E. Maerker, F. J. Muckenthaler, and P. N. Stevens

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 411-422

Technical Paper / dx.doi.org/10.13182/NSE67-A18280

Monte Carlo Calculations, Using the Albedo Concept, of the Fast-Neutron Dose Rates along the Center Lines of One- and Two-Legged Square Concrete Open Ducts and Comparison with Experiment

R. E. Maerker and F. J. Muckenthaler

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 423-433

Technical Paper / dx.doi.org/10.13182/NSE67-A18281

On the Attenuation of Neutrons and Photons Duct Filled with a Helical Steel Plug

E. Aalto and Å. Krell

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 433-440

Technical Paper / dx.doi.org/10.13182/NSE67-A18282

Albedo Component of Gamma Rays Passing Through a Cylindrical Duct

Y. Higashihara, Masaru Nakai, Masanori Okubo,

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 441-449

Technical Paper / dx.doi.org/10.13182/NSE67-A18283

Gamma-Ray Streaming Through a Straight Cylindrical Duct

Mitsuo Shindo, Akira Tsuruo, Shun-ichi Miyasaka, Mitsuyuki Kitazume, Jun-ichi Miyakoshi

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 450-463

Technical Paper / dx.doi.org/10.13182/NSE67-A18284

Weight Optimization of Gamma-Ray Shields Using Layered Media and Spherical Geometry

Alfred F. Rohach

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 464-466

Technical Note / dx.doi.org/10.13182/NSE67-A18285

Empirical Formulas for Secondary-Nucleon-Production Cross Sections

W. R. Yucker

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Page 467

Technical Note / dx.doi.org/10.13182/NSE67-A18286

Few-Group and Multigroup Calculations of Neutron Penetration

K. Shure

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 468-471

Technical Note / dx.doi.org/10.13182/NSE67-A18287

Heating in Infinite Cylinders by Uniform Gamma-Ray Sources

C. W. Nestor, Jr., and H. C. Claiborne

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 472-474

Technical Note / dx.doi.org/10.13182/NSE67-A18288

A Markov Matrix Treatment of Neutron Diffusion in Thin Slabs

M. L. Eaton and C. M. Huddleston

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 475-477

Technical Note / dx.doi.org/10.13182/NSE67-A18289

Differential Neutron Albedo For Finite Slabs

Duane R. Doty

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 478-480

Technical Note / dx.doi.org/10.13182/NSE67-A18290

A Modified Formula for Differential Exposure Albedo for Gamma Rays Reflected from Concrete

A. B. Chilton

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 481-482

Technical Note / dx.doi.org/10.13182/NSE67-A18291

Air-Ground Interface Effects on the Exposure from Elevated ¹³⁷Cs y Sources

C. E. Clifford and G. D. Wait

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 483-484

Technical Note / dx.doi.org/10.13182/NSE67-A18292

The Small-Angle Limit for Twice-Scattered Gamma Rays from a Point-lsotropic Source

Edgar E. Morris and L. V. Spencer

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 485-487

Technical Note / dx.doi.org/10.13182/NSE67-A18293