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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Three nations, three ways to recycle plastic waste with nuclear technology
Plastic waste pollutes oceans, streams, and bloodstreams. Nations in Asia and the Pacific are working with the International Atomic Energy Agency through the Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative to tackle the problem. Launched in 2020, NUTEC Plastics is focused on using nuclear technology to both track the flow of microplastics and improve upstream plastic recycling before discarded plastic can enter the ecosystem. Irradiation could target hard-to-recycle plastics and the development of bio-based plastics, offering sustainable alternatives to conventional plastic products and building a “circular economy” for plastics, according to the IAEA.
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Measurements of the 59Ni(n,α) Cross Section for Thermal Neutrons
H. M. Eiland and G. J. Kirouac
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 1-8
Technical Paper | doi.org/10.13182/NSE74-A23326
Measurement and Calculation of Integral Heavy-Element Cross-Section Ratios in the Fast Breeder Reactor EBR-II
N. D. Dudey, D. Meneghetti, R. R. Heinrich, R. H. Rempert
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 9-26
Technical Paper | doi.org/10.13182/NSE74-A23327
Measurement of Steady-State, Space-Dependent, Thermal-Neutron Spectra in Beryllium Assemblies with Strong Transverse Leakage
J. A. Lake, J. M. Kallfelz
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 27-46
Technical Paper | doi.org/10.13182/NSE74-A23328
Measurements of Equilibrium and Time-Dependent Energy Spectra of Beta Rays from Californium-252 Fission Fragments
R. A. Knief, B. W. Wehring, M. E. Wyman
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 47-60
Technical Paper | doi.org/10.13182/NSE74-A23329
Model for Calculating Prompt-Response Self-Powered Neutron Detectors
W. Jaschik, L W. Seifritz
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 61-78
Technical Paper | doi.org/10.13182/NSE74-A23330
A Criticality Study of Fissile-Metal and Fissile-Solution Combinations
D. C. Hunt, Robert E. Rothe
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 79-92
Technical Paper | doi.org/10.13182/NSE74-A23331
Numerical Solution of the Linear Integral Boltzmann Equation
Dermott E. Cullen
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 93-106
Technical Paper | doi.org/10.13182/NSE74-A23332
The Permeability Minimum and the Viscosity of Gases at Low Pressure
E. Creutz
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 107-109
Technical Paper | doi.org/10.13182/NSE74-A23333
Calculated and Measured Dose Buildup Factors for Gamma Rays Penetrating Multilayered Slabs
Gail de P. Burke and Harold L. Beck
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 109-112
Technical Paper | doi.org/10.13182/NSE74-A23334
Modified One-Mode Method for Fast-Reactor Diffusion Calculations
Takashi Kiguchi
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 112-120
Technical Paper | doi.org/10.13182/NSE74-A23335
The Continued Fraction Approximation: A Time-Dependent Transport Method
William A. Yingling, Charles J. Bridgman
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 123-136
Technical Paper | doi.org/10.13182/NSE74-A23338
Exact Time-Dependent Spatial and Legendre Moments for the Monoenergetic Transport Equation
E. H. Canfield
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 137-140
Technical Paper | doi.org/10.13182/NSE74-A23339
An Analytical Estimate of the Error in Conventional Point-Kinetics Reactivity Due to Spatial Effects
George E. Apostolakis
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 141-152
Technical Paper | doi.org/10.13182/NSE74-A23340
Neutron Slowing Down via Inelastic Scattering in Heavy Moderators—I. Steady State
Michael J. Lineberry, Noel Corngold
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 153-161
Technical Paper | doi.org/10.13182/NSE74-A23341
Gamma-Ray Heating Measurements in Zero-Power Fast Reactors with Thermoluminescent Dosimeters
G. G. Simons, T. J. Yule
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 162-175
Technical Paper | doi.org/10.13182/NSE74-A23342
Analyses and Measurements of Gamma-Ray Heating in the Demonstration Benchmark Plutonium-Fueled Critical Assembly
G. G. Simons, A. P. Olson
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 176-196
Technical Paper | doi.org/10.13182/NSE74-A23343
Moments Method Calculations of Neutron Distributions in Concrete
G. L. Simmons, C. Eisenhauer
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 197-219
Technical Paper | doi.org/10.13182/NSE74-A23344
Early Time Air Fireball Model for Near Surface Energy Release
G. C. Pomraning
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 220-225
Technical Paper | doi.org/10.13182/NSE74-A23345
An Algorithm for the Energy Deposition by Fast Electrons
Tatsuo Tabata, Rinsuke Ito
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 226-239
Technical Paper | doi.org/10.13182/NSE74-A23346
Pool Boiling in Subcooled Sodium at Atmospheric Pressure
M. M. K. Farahat, Donald T. Eggen, Donn R. Armstrong
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 240-254
Technical Note | doi.org/10.13182/NSE74-A23347
A New Form of the BN Transport Equations
J. Ligou, J. Stepanek
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 255-256
Technical Note | doi.org/10.13182/NSE74-A23348
Angle Selection Techniques for Gamma Photons in Monte Carlo Calculations on Parallel Computers
G. P. Cavanaugh, A. B. Chilton
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 256-261
Technical Note | doi.org/10.13182/NSE74-A23349
Deposition of Energy in U, UC, and UO2 Fuels
K. B. Winterbon
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 261-262
Technical Note | doi.org/10.13182/NSE74-A23350
On the Effects of Heat Transfer upon Collapsing Bubbles
Terry Mitchell, Frederick G. Hammitt
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 263-276
Technical Paper | doi.org/10.13182/NSE74-A23352
Neutron-Induced Gamma-Ray Production in Calcium in the Energy Range 0.7 ≤ En ≤ 20 MeV
J. K. Dickens, T. A. Love, G. L. Morgan
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 277-284
Technical Paper | doi.org/10.13182/NSE74-A23353
Transport Analysis of Measured Neutron Leakage Spectra from Spheres as Tests of Evaluated High-Energy Cross Sections
Donald Bogart, Donald F. Shook, Daniel Fieno
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 285-303
Technical Paper | doi.org/10.13182/NSE74-A23354
Cross-Section Sensitivity of Breeding Ratio in a Fusion-Reactor Blanket
D. E. Bartine, R. G. Alsmiller, Jr., E. M. Oblow, F. R. Mynatt
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 304-318
Technical Paper | doi.org/10.13182/NSE74-A23355
Transmutation of Massive Loadings of Cesium-137 in the Blanket of a Controlled Thermonuclear Reactor
B. F. Gore, B. R. Leonard, Jr.
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 319-323
Technical Note | doi.org/10.13182/NSE74-A23356
Calculated Secondary-Particle Spectra from Alpha-Particle- and Carbon-Induced Nuclear Reactions
T. A. Gabriel, R. T. Santoro, H. W. Bertini, N. M. Larson
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 323-325
Technical Note | doi.org/10.13182/NSE74-A23357
The Effective Half-Life of Californium-252
V. Spiegel
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 326-327
Technical Note | doi.org/10.13182/NSE74-A23358
An Iterated Sequential Transport Approximation for Anisotropic Spectral Moments
D. C. Gibbs, M. Becker, B. K. Malaviya
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 327-329
Technical Note | doi.org/10.13182/NSE74-A23359
Transport Equation in an Accelerated Material, Legendre Moments, and a Diffusion Approximation
B. R. Wienke
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 329-332
Technical Note | doi.org/10.13182/NSE74-A23360
Forward-Adjoint Coupling as a Means of Solving Three-Dimensional Deep-Penetration Transport Problems
C. O. Slater, J. C. Robinson
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 332-337
Technical Note | doi.org/10.13182/NSE74-A23361
Few-Group Methods for Fast-Reactor Transients
William B. Terney, R. Srivenkatesan
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 337-347
Technical Note | doi.org/10.13182/NSE74-A23362
Solution of Standard Diamond Difference Equations for Discrete-Ordinate Neutron Transport Equations Equivalent to the PL Approximation in x-y Geometry
Jungchung Jung, Nobuo Ohtani, Keisuke Kobayashi, Hiroshi Nishihara
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 355-369
Technical Paper | doi.org/10.13182/NSE74-A23369
Relative and Absolute Measurements of the Fast-Neutron Fission Cross Section of Uranium-235
W. P. Poenitz
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 370-392
Technical Paper | doi.org/10.13182/NSE74-A23370
The Use of Californium-252 as a Randomly Pulsed Neutron Source for Prompt-Neutron Decay Measurements
J. T. Mihalczo
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 393-414
Technical Paper | doi.org/10.13182/NSE74-5
A Study of the 2.8-keV Neutron Resonance of Sodium and an Analysis of the Total Neutron Cross Section up to 50 keV
Janet Seltzer, W. K. Firk
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 415-419
Technical Paper | doi.org/10.13182/NSE74-A23372
Fine Neutron-Spectrum Effects on Spatial Calculations for Fast-Reactor Design
R. Corcuera, A. Khairallah
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 420-435
Technical Paper | doi.org/10.13182/NSE74-A23373
A Method of Computing Fission-Product Decay Heat in a Reactor with Time-Dependent Flux
F. W. Barclay, K. W. Dormuth
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 436-439
Technical Paper | doi.org/10.13182/NSE74-A23374
SINOD—A Nonlinear Lumped-Parameter Model for Steady-State, Transient, and Stability Analysis of Two-Phase Flow in Natural Circulation Boiling-Water Loops
M. R. Mataušek
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 440-457
Technical Paper | doi.org/10.13182/NSE74-A23375
Radiation-Induced Boiling in Superheated Water and Organic Liquids
C. R. Bell, N. P. Oberle, W. Rohsenow, N. Todreas, C. Tso
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 458-465
Technical Paper | doi.org/10.13182/NSE74-A23376
Equations of Motion of a Liquid-Submerged Sonic Gas Jet Relative to Fission-Gas-Jet Impingement in Subassemblies of the Liquid Metal Fast Breeder Reactor
T. C. Chawla
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 466-474
Technical Paper | doi.org/10.13182/NSE74-A23377
Reciprocity Relations in Response Matrix Theory
Sten-Örjan Lindahl
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 475-478
Technical Note | doi.org/10.13182/NSE74-A23378
The Effect of Local Flux Distortions on the Doppler Effect of Small Fissile Samples
P. H. Kier, M. Salvatores
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 479-482
Technical Note | doi.org/10.13182/NSE74-A23379
Relationships Between Experimental and Theoretical Parameters in Unresolved Resonance Theory
M. Gyulassy, S. T. Perkins
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 482-486
Technical Note | doi.org/10.13182/NSE74-A23380
An Assessment of Proposed (n, γn<’) Data Based on Measured and Calculated Neutron Spectra in Uranium Depleted in Uranium-235
Martin Becker, Narinder N. Kaushal
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 487-488
Technical Note | doi.org/10.13182/NSE74-A23381
