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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
Standards Program
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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Latest News
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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Temperature Dynamic Analysis of Fuel Elements for Boiling Water Reactors
M. G. Zaalouk, A. M. Mitry, W. C. Peterson
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE74-A23387
Some Aspects of Fuel-Pin-Failure Propagation in Sodium-Cooled Fast Reactors
Hans K. Fauske
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 10-17
Technical Paper | doi.org/10.13182/NSE74-A23388
The Thermal-Neutron Scattering Cross Sections of Uranium-233 and Thorium-232
L. Green, J. A. Mitchell
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 18-27
Technical Paper | doi.org/10.13182/NSE74-A23389
Age of Californium-252 Fission Neutrons to Indium Resonance Energy in Water
V. Spiegel
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 28-34
Technical Paper | doi.org/10.13182/NSE74-A23390
Sensitivity of a Fast Critical Assembly to Uncertainties in Input Data Determined by Perturbation Theory
H. H. Hummel, W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 35-46
Technical Paper | doi.org/10.13182/NSE74-A23391
Simulation Studies of a Practical Reactor Control System Providing Time-Optimal Shutdown
E. Corran, C. A. Stapleton
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 47-54
Technical Paper | doi.org/10.13182/NSE74-A23392
An Examination of Some Approximations for Heterogeneous Reactors
Hugh K. Clark
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 55-71
Technical Paper | doi.org/10.13182/NSE74-A23393
Effects of Highly Anisotropic Scattering on Monoenergetic Neutron Transport at Deep Penetrations
E. Oblow, K. Kin, H. Goldstein, J. J. Wagschal
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 72-84
Technical Paper | doi.org/10.13182/NSE74-A23394
Legendre Polynomial Expansion of the Klein-Nishina Differential Cross Section
K. E. Weise, A. Foderaro
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 85-93
Technical Paper | doi.org/10.13182/NSE74-A23395
Benchmark Values for the Slab and Sphere Criticality Problem in One-Group Neutron Transport Theory
Hans G. Kaper, Arthur J. Lindeman, Gary K. Leaf
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 94-99
Technical Note | doi.org/10.13182/NSE54-94
Relativistic Compton Scattering by the Discrete Ordinates Method
Brian G. Stephan, Charles J. Bridgman
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 101-115
Technical Paper | doi.org/10.13182/NSE74-A23399
Single-Level Analysis of the Uranium-233 Fission Cross Section for Neutron Energies Between 6 and 124 eV
S. Nizamuddin, J. Blons
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 116-126
Technical Paper | doi.org/10.13182/NSE74-A23400
Neutron Pulses Slowing Down in Heavy Media Analysis with Applications of the Lead Spectrometer
Mohamed Sawan, Robert W. Conn
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 127-142
Technical Paper | doi.org/10.13182/NSE74-A23401
Correcting for Emission-Time Effects in Neutron Time-of-Flight Data Using Multiple Time Spectra
H. A. Robitaille, J. S. Hewitt
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 143-156
Technical Paper | doi.org/10.13182/NSE74-A23402
Estimation of Reactivity Worths by Local Calculation
M. J. Lineberry
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 157-165
Technical Paper | doi.org/10.13182/NSE74-A23403
Minimal Time Control of Spatial Xenon Oscillations in Nuclear Power Reactors
A. A. El-Bassioni, C. G. Poncelet
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 166-176
Technical Paper | doi.org/10.13182/NSE74-A23404
Calculation of the Decay Power of Fission Products
Kanji Tasaka, Nobuo Sasamoto
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 177-189
Technical Paper | doi.org/10.13182/NSE74-A23405
Cross Section for the Delayed-Neutron Yield from the 9Be(n, p) 9Li Reaction at Neutron Energies of 14.5 and 14.9 MeV
R. H. Augustson, H. O. Menlove
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 190-191
Technical Note | doi.org/10.13182/NSE74-A23406
Neutron-Induced Gamma-Ray Production in Titanium for Incident-Neutron Energies of 4.9, 5.4, and 5.9 MeV
J. K. Dickens
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 191-196
Technical Note | doi.org/10.13182/NSE74-A23407
Functionals to Represent the Neutron Flux in Fast Pulsed Assemblies
Harold N. Knickle, Paul B. Daitch
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 196-200
Technical Note | doi.org/10.13182/NSE74-A23408
Flux Synthesis Calculations for Fast Reactors
C. H. Adams, W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 201-206
Technical Note | doi.org/10.13182/NSE74-A23409
Application of an Improved Time-Difference Method for Spatial Xenon Transient Analysis
John C. Lee
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 206-214
Technical Note | doi.org/10.13182/NSE74-A23410
Critical Heat Flux and Pressure Drop Tests with Parallel Upflow of High Pressure Water in Bundles of Twenty ¾-in. Rods
B. W. LeTourneau, M. E. Gavin, S. J. Green
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 214-232
Technical Note | doi.org/10.13182/NSE74-A23411
Prediction of Gamma-Ray Spectra at Deep Penetration Utilizing the Equilibrium Angular Distribution
D. M. Johnson
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 235-253
Technical Paper | doi.org/10.13182/NSE74-A23415
Experimental Evidence of an Equilibrium Property in Gamma-Ray Angular Spectra Penetrating Bulk Shields
D. M. Johnson, P. B. Woollam
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 254-262
Technical Paper | doi.org/10.13182/NSE74-A23416
The Yield of Short-Lived Gamma-Ray Emitting Nuclides from Fast- and Thermal-Neutron Fission
R. P. Larsen, N. D. Dudey, R. R. Heinrich, R. D. Oldham, R. J. Armani, R. J. Popek, R. Gold
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 263-272
Technical Paper | doi.org/10.13182/NSE74-A23417
Cobalt Fast-Neutron Cross Sections
P. T. Guenther, P. A. Moldauer, A. B. Smith, J. F. Whalen
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 273-285
Technical Paper | doi.org/10.13182/NSE74-A23418
Neutron Cross Sections of Samarium-147 and Samarium-150
H. M. Eiland, S. Weinstein, K. W. Seemann
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 286-299
Technical Paper | doi.org/10.13182/NSE74-A23419
Evaluation of Uranium-238 Neutron Cross Sections from Spectral Measurements
H. Bluhm, G. Fieg, H. Werle
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 300-316
Technical Paper | doi.org/10.13182/NSE74-A23420
The Ratio of the Uranium-233 to Uranium-235 Fission Cross Section
J. W. Meadows
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 317-321
Technical Paper | doi.org/10.13182/NSE74-1
Total Neutron Cross Sections of Uranium-235, Uranium-238, and Plutonium-239 from 0.5 to 15 MeV
R. B. Schwartz, R. A. Schrack, H. T. Heaton, II
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 322-326
Technical Paper | doi.org/10.13182/NSE74-A23422
Anisotropic Neutron Diffusion in Lattices of the Zero-Power Plutonium Reactor Experiments
Ely M. Gelbard
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 327-340
Technical Paper | doi.org/10.13182/NSE74-A23423
A Theory for Pulsed-Neutron Experiments in Reactor Lattices
J. J. Van Binnebeek
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 341-352
Technical Paper | doi.org/10.13182/NSE74-A23424
A Solution of the Milne Problem Using Full-Range Completeness of Case’s Eigenfunctions
S. K. Loyalka
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 353-356
Technical Paper | doi.org/10.13182/NSE74-A23425
Axial Neutron Streaming in Gas-Cooled Fast Reactors
P. Köhler, J. Ligou
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 357-360
Technical Note | doi.org/10.13182/NSE74-A23426
The Effect of Position on the Criticality of Uranium Spheres in Uranium Solution Cylinders
Robert E. Rothe, D. C. Hunt
Nuclear Science and Engineering | Volume 54 | Number 3 | July 1974 | Pages 360-366
Technical Note | doi.org/10.13182/NSE74-A23427
Generalized Collision Probabilities and Neutron Transport Eigenvalue Problems
Tomas Lefvert
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 369-375
Technical Paper | doi.org/10.13182/NSE74-A23431
Weighted Central Difference Equations for the Neutron Transport Equation
Niel K. Madsen
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 376-386
Technical Paper | doi.org/10.13182/NSE74-A23432
Calculation of the Flux Variation and the Reactivity Change Induced by a Central Perturbation in a Fast Critical Assembly The Reduced Reactor Model
D. Akl, B. Laponche
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 387-394
Technical Paper | doi.org/10.13182/NSE74-A23433
Neutron and Gamma-Ray Effects on Self-Powered In-Core Radiation Detectors
H. D. Warren, N. H. Shah
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 395-415
Technical Paper | doi.org/10.13182/NSE74-A23434
Small-Angle Scattering of 7.4- to 9.5-MeV Neutrons from Nitrogen and Oxygen
W. P. Bucher, C. E. Hollandsworth, D. McNatt, R. Lamoreaux, A. Niiler, J. E. Youngblood
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 416-422
Technical Paper | doi.org/10.13182/NSE74-A23435
Measurement and Normalization of the Relative Uranium-233 Fission Cross Section in the Low Resonance Region
A. J. Deruytter, C. Wagemans
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 423-431
Technical Paper | doi.org/10.13182/NSE74-A23436
Accurate Kinetics Equations of a Square Cascade for Gas Separation
S. Yamashita
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 432-444
Technical Paper | doi.org/10.13182/NSE74-A23437
Turbulence Measurements in a Magneto-Fluid-Mechanic Channel
Hsichun M. Hua, Paul S. Lykoudis
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 445-449
Technical Paper | doi.org/10.13182/NSE74-A23438
Partial-Range Analysis of the One-Speed Neutron Transport Equation with Anisotropic Scattering
E. A. Attia, A. A. Harms
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 450-455
Technical Note | doi.org/10.13182/NSE74-A23439
An Asymptotic Solution in the Theory of Neutron Moderation
C. E. Siewert, A. R. Burkart
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 455-456
Technical Note | doi.org/10.13182/NSE74-A23440
Application of the Finite Element Method to Two-Dimensional Diffusion Problems
L. O. Deppe, K. F. Hansen
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 456-465
Technical Note | doi.org/10.13182/NSE74-A23441
A Rapid Calculational Method for Multigroup Elastic Transfer
Martin Becker
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 465-467
Technical Note | doi.org/10.13182/NSE74-A23442
On the Estimation of Errors in Reactor Theory
Yigal Ronen
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 467-470
Technical Note | doi.org/10.13182/NSE74-A23443
Neutron Yields from Uranium Isotopes in Uranium Hexafluoride
Thomas E. Sampson
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 470-474
Technical Note | doi.org/10.13182/NSE54-470
Optimization of Control-Rod Programming in Multiregion Nuclear Reactors
Koichi Sekimizu, Kazuo Monta
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 474-481
Technical Note | doi.org/10.13182/NSE74-A23445
On the Mechanisms for Vapor Explosions
S. G. Bankoff, H. K. Fauske
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 481-482
Technical Note | doi.org/10.13182/NSE74-A23446
