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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
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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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Senate committee hears from energy secretary nominee Chris Wright
Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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A Possible Estimation of In-Process Inventory in Enrichment Cascades
I. Kiss, Sz. Vass
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 1-5
Technical Paper | doi.org/10.13182/NSE79-A21278
Angular Effects in Toroidal Diffusion
G. C. Pomraning
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 6-13
Technical Paper | doi.org/10.13182/NSE79-A21279
Theoretical Variations in the Concentration of Tritium in the Heavy Water in CANDU Reactors Caused by the 3He(n,p)3H Reaction
R. M. Holford, R. V. Osborne
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 14-21
Technical Paper | doi.org/10.13182/NSE79-A21280
Elastic and Inelastic Scattering of 7- to 14-MeV Neutrons from Lithium-6 and Lithium-7
H. H. Hogue, P. L. von Behren, D. W. Glasgow, S. G. Glendinning, P. W. Lisowski, C. E. Nelson, F. O. Purser, W. Tornow, C. R. Gould, L. W. Seagondollar
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 22-29
Technical Paper | doi.org/10.13182/NSE79-A21281
Neutron Total Cross-Section Measurements of 9Be, 10,11B, and 12,13C from 1.0 to 14 MeV Using the 9Be(d,n)10B Reaction as a “White” Neutron Source
G. F. Auchampaugh, S. Plattard, N. W. Hill
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 30-38
Technical Paper | doi.org/10.13182/NSE79-A21282
Neutron Capture Cross-Section Ratios of Plutonium-240 and Plutonium-242 Versus Gold-197 in the Energy Range from 50 to 250 keV
K. Wisshak, F. Käppeler
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 39-46
Technical Paper | doi.org/10.13182/NSE79-A21283
A Measurement of the Subthreshold Neutron Fission Cross Section of Plutonium-240 in the Energy Range from 10 to 250 keV
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 47-54
Technical Paper | doi.org/10.13182/NSE79-A21284
Fick's Law and the Neutron Slowing Down Length in Hydrogenous Moderators
Carlos Gago B.
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 55-64
Technical Paper | doi.org/10.13182/NSE79-A21285
Determination of Power Reactor Resonance by the Rod-Drop Method
Edward L. H. Tang
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 65-75
Technical Paper | doi.org/10.13182/NSE79-A21286
Monte Carlo Source Biasing Optimization
T. J. Hoffman
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 76-77
Technical Paper | doi.org/10.13182/NSE79-A21287
An Empirical Formula Predicting Shutdown Dose Rate of the Recirculation Pipes in Boiling Water Reactors
Shunsuke Uchida, Masao Kitamura, Makoto Kukuchi, Hideo Yusa, Katsumi Ohsumi, Yasunori Matsushima
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 78-85
Technical Note | doi.org/10.13182/NSE79-A21288
Effects of Energy Losses of Arbitrary Magnitude on Fuel Quality, Vapor Density, and Bubble Diameter in an Idealized Expansion of Mixtures of UO2 and Sodium
Hugo W. Bertini, Janice S. White
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 85-94
Technical Note | doi.org/10.13182/NSE79-A21289
On the Stability of the Flow of Thin Liquid-Lithium Films
James E. Howard
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 94-99
Technical Note | doi.org/10.13182/NSE79-A21290
Helium Production in Stainless Steel
B. Goel
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 99-104
Technical Note | doi.org/10.13182/NSE79-A21291
The Importance of Subthreshold Fission Phenomena in Certain Applications of Fission Threshold Detectors: An Example of Neptunium-237 for Nondestructive Assay
F. C. Difllippo, G. L. Ragan
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 104-107
Technical Note | doi.org/10.13182/NSE79-A21292
Effect of 6Li + 6Li Reactions in a Fusion Reactor Operating on 6Li(p, α)3He
Lawrence Ruby, Tai-Ping Lung
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 107-109
Technical Note | doi.org/10.13182/NSE79-A21293
Measurement of Cross Sections for the 27Al(n, n′γ)27Al Reaction Near Threshold
Donald L. Smith
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 109-114
Technical Note | doi.org/10.13182/NSE79-A21294
Eigenvalue Spectrum of Multiplying Slabs and Spheres for Monoenergetic Neutrons with Anisotropic Scattering
E. B. Dahl, N. G. Sjöstrand
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 114-125
Technical Note | doi.org/10.13182/NSE69-114
Neutron-Induced Fission in a DT-Plutonium Plasma. Part I: Fission Fragment Slowing Down
S. T. Perkins
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 137-146
Technical Paper | doi.org/10.13182/NSE79-A20605
Neutron-Induced Fission in a DT-Plutonium Plasma. Part II: Enhancement of Neutron Production and Fusion Rate
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 147-155
Technical Paper | doi.org/10.13182/NSE79-A20606
The FN Method in Neutron-Transport Theory. Part I: Theory and Applications
C. E. Siewert, P. Benoist
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 156-160
Technical Paper | doi.org/10.13182/NSE79-1
The FN Method in Neutron-Transport Theory. Part II: Applications and Numerical Results
P. Grandjean, C. E. Siewert
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 161-168
Technical Paper | doi.org/10.13182/NSE79-A20608
Spectral Fine-Structure Effects on Material and Doppler Reactivity Worths
E. Greenspan, Y. Karni
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 169-190
Technical Paper | doi.org/10.13182/NSE79-A20609
Neutron Scattering Cross Sections of Uranium-238
L. E. Beghian, G. H. R. Kegel, T. V. Marcella, B. K. Barnes, G. P. Couchell, J. J. Egan, A. Mittler, D. J. Pullen, W. A. Schier
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 191-201
Technical Paper | doi.org/10.13182/NSE79-A20610
Measurement and Resonance Analysis of Neutron Transmission Through Uranium-238
D. K. Olsen, G. de Saussure, R. B. Perez, F. C. Difilippo, R. W. Ingle, H. Weaver
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 202-222
Technical Paper | doi.org/10.13182/NSE79-A20611
Differential Neutron Scattering Cross Sections of Lithium-6 and Lithium-7 for Neutrons of 4 to 7.5 MeV Energy
H. D. Knox, R. M. White, R. O. Lane
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 223-230
Technical Paper | doi.org/10.13182/NSE79-A20612
Critical Experiments on Light Water Lattices of UO2 and Gd2O3 Rods
Tohru Haga, Sadao Hanazawa, Toshio Kimura
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 231-244
Technical Paper | doi.org/10.13182/NSE79-A20613
Criticality of a Slab Reactor with Finite Reflectors
Trine-Yie Dawn
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 245-250
Technical Paper | doi.org/10.13182/NSE79-A20614
A Model for the Prediction of Shutdown Margin for Boiling Water Reactors
Warren F. Witzig, Ross T. Thomas
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 251-263
Technical Paper | doi.org/10.13182/NSE79-A20615
Fast Integral Modeling of Hypothetical Core Disruptive Accidents in Liquid-Metal Fast Breeder Reactors
C. J. Mueller, J. K. Vaurio
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 264-278
Technical Paper | doi.org/10.13182/NSE79-A20616
Network Computations Using a Transient Two-Phase Velocity Difference Model
Robert W. Lyczkowski, Delwin C. Mecham, Charles W. Solbrig
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 279-289
Technical Paper | doi.org/10.13182/NSE79-A20617
Laminar, Transition, and Turbulent Parallel Flow Pressure Drop Across Wire-Wrap-Spaced Rod Bundles
F. C. Engel, R. A. Markley, A. A. Bishop
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 290-296
Technical Paper | doi.org/10.13182/NSE79-A20618
Multichannel Model for Relocation of Molten Fuel Cladding in Unprotected Loss-of-Flow Accidents in Liquid-Metal Fast Breeder Reactors
M. Ishii, W. L. Chen, M. A. Grolmes
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 297-318
Technical Paper | doi.org/10.13182/NSE79-2
Pressure Pulses Generated by Gas Released from a Breached Fuel Element
Ting-Shu Wu
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 319-325
Technical Paper | doi.org/10.13182/NSE79-A20620
Introduction of the Quasi-Static Synthesis Method for Solution of Space-Time Reactor Kinetics Problems
Bruce I. Hauss, William E. Kastenberg
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 326-333
Technical Note | doi.org/10.13182/NSE79-A20621
Measurement and Calculation of Average Activation Cross Sections in the Spontaneous Fission Neutron Field of 252Cf
W. Mannhart, W. G. Alberts
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 333-338
Technical Note | doi.org/10.13182/NSE79-A20622
Exact Statistical Analysis of Nonlinear Dynamic Power Reactor Models by the Fokker-Planck Method. Part II: Reactor with On-Off Control
A. F. Debosscher, W. L. Dutre
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 347-353
Technical Paper | doi.org/10.13182/NSE79-A19951
Exact Statistical Analysis of Nonlinear Dynamic Power Reactor Models by the Fokker-Planck Method. Part III: Reactor with Temperature Feedback
A. F. Debosscher
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 354-362
Technical Paper | doi.org/10.13182/NSE79-A19952
A Random Geometry Model in Criticality Calculations of Solutions Containing Raschig Rings
Shi-Ping Teng, Duaine G. Lindstrom
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 363-366
Technical Paper | doi.org/10.13182/NSE79-A19953
Neutron Diffusion in Water Containing 1/v and Non-1/v Absorbers
R. M. Bansal, S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 367-374
Technical Paper | doi.org/10.13182/NSE79-A19954
Total Neutron Cross Section for Americium-241
Thomas W. Phillips, Robert E. Howe
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 375-377
Technical Paper | doi.org/10.13182/NSE79-A19955
Neutron-Photon Multigroup Cross Sections for Neutron Energies 60 MeV
R. G. Alsmiller, Jr., J. Barish
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 378-388
Technical Paper | doi.org/10.13182/NSE79-A19956
Application of Least-Squares Method to Decay Heat Evaluation
F. Schmittroth, R. E. Schenter
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 389-397
Technical Paper | doi.org/10.13182/NSE79-A19957
The Development of Maneuvering Strategies Using Optimal Control Theory
D. D. Ebert, W. B. Terney, E. A. Williamson, Jr., N. R. Gomm
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 398-410
Technical Paper | doi.org/10.13182/NSE79-A19958
Experiments and Nonequilibrium Analysis of Pipe Blowdown
W. S. Winters, Jr., H. Merte, Jr.
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 411-429
Technical Paper | doi.org/10.13182/NSE79-A19959
Complex Buckling Modes in Asymmetric Cell lattices
R. P. Hughes
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 430-432
Technical Note | doi.org/10.13182/NSE79-A19960
Gamma-Ray Dose Rate Conversion and Buildup Factors
K. Shure
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 432-436
Technical Note | doi.org/10.13182/NSE79-A19961
Tchebycheff-Fitted Berger Coefficients for Eisenhauer-Simmons Gamma-Ray Buildup Factors in Ordinary Concrete
A. B. Chilton
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 436-438
Technical Note | doi.org/10.13182/NSE79-A19962
Inertial Confinement Fusion and Long-Term Nuclear Waste Management
Heiner Meldner
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 438-441
Technical Note | doi.org/10.13182/NSE79-A19963
