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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
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 Split-Matrix Method for the Numerical Solution of Two-Phase Flow Equations
Peter Romstedt
Nuclear Science and Engineering | Volume 104 | Number 1 | January 1990 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE90-A23696
Fast Three-Dimensional Core Model for Digital Control in Boiling Water Reactors
O. Lupas, D. Beraha
Nuclear Science and Engineering | Volume 104 | Number 1 | January 1990 | Pages 10-25
Technical Paper | doi.org/10.13182/NSE90-A23697
Optimized Two-Dimensional Sn Transport (BISTRO)
G. Palmiotti, J. M. Rieunier, C. Gho, M. Salvatores
Nuclear Science and Engineering | Volume 104 | Number 1 | January 1990 | Pages 26-33
Technical Paper | doi.org/10.13182/NSE90-1
Thermal Disadvantage Factor: An Efficient Calculation
K. M.-S. Abdullah, S. K. Loyalka
Nuclear Science and Engineering | Volume 104 | Number 1 | January 1990 | Pages 34-39
Technical Paper | doi.org/10.13182/NSE90-A23699
Energy Dependence of Neutron Self-Shielding Factors in an Isolated Resonance
Maria Do Carmo Lopes, Jorge Molina Avila
Nuclear Science and Engineering | Volume 104 | Number 1 | January 1990 | Pages 40-45
Technical Paper | doi.org/10.13182/NSE90-A23700
Iron and Cadmium Capture Gamma-Ray Photofission Measurements
T. G. Williamson, G. P. Lamaze, D. M. Gilliam, C. M. Eisenhauer
Nuclear Science and Engineering | Volume 104 | Number 1 | January 1990 | Pages 46-52
Technical Paper | doi.org/10.13182/NSE90-A23701
Measurement of Prompt Neutron Decay Constant and Large Subcriticality by the Feynman-α Method
Tsuyoshi Misawa, Seiji Shiroya, Keiji Kanda
Nuclear Science and Engineering | Volume 104 | Number 1 | January 1990 | Pages 53-65
Technical Paper | doi.org/10.13182/NSE104-53
Feasibility and Incentives for Burnup Credit in Spent-Fuel Transport Casks
Thomas L. Sanders, R. Michael Westfall
Nuclear Science and Engineering | Volume 104 | Number 1 | January 1990 | Pages 66-77
Technical Paper | doi.org/10.13182/NSE90-A23703
Global Optimization and Sensitivity Analysis
Dan G. Cacuci
Nuclear Science and Engineering | Volume 104 | Number 1 | January 1990 | Pages 78-88
Technical Paper | doi.org/10.13182/NSE90-A23704
A Synthetically Accelerated Weighted Diamond Scheme for Charged-Particle Transport Calculations
J. J. Honrubia, J. E. Morel
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 91-111
Technical Paper | doi.org/10.13182/NSE90-A23707
A Fundamental Derivation of the Nodal Diffusion Equation and Its Variation
Hoju Moon, Samuel H. Levine
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 112-122
Technical Paper | doi.org/10.13182/NSE90-A23708
Harmonic Analysis of Stochastic Descriptors and the Interpretation of 252Cf Neutron Source Experiments
Felix C. Difilippo
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 123-134
Technical Paper | doi.org/10.13182/NSE90-A23709
Interpretation of Noise Coherence Function Measurements in Liquid-Metal Fast Breeder Reactor Critical Assemblies
Toshio Sanda
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 135-144
Technical Paper | doi.org/10.13182/NSE90-A23710
A Method for Projecting Integral Measured Quantities
D. K. Wehe, J. Schmidt
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 145-152
Technical Paper | doi.org/10.13182/NSE90-A23711
Parity Simulation of Single-Phase Thermal Hydraulics
Eduardo V. Depiante, John E. Meyer
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 153-168
Technical Paper | doi.org/10.13182/NSE90-A23712
Two-Phase Thermal-Hydraulic Analysis Using Parity Simulation
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 169-182
Technical Paper | doi.org/10.13182/NSE90-A23713
Some Findings in Neutron Multiplication Factor Monitoring
Pedro A. Landeyro, Tadeusz Zoltowski
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 183-187
Technical Note | doi.org/10.13182/NSE90-A23714
Effective Cross Sections and Sources in Moving Material
B. R. Wienke, T. R. Hill
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 188-196
Technical Note | doi.org/10.13182/NSE90-A23715
A Numerical Method for One-Group Slab-Geometry Discrete Ordinates Problems with No Spatial Truncation Error
Ricardo C. De Barros, Edward W. Larsen
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 199-208
Technical Paper | doi.org/10.13182/NSE90-A23719
Analytic Reductions for Transmission and Leakage Probabilities in Finite Tubes and Hexahedra
G. Marleau, R. Roy, A. Hébert
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 209-216
Technical Paper | doi.org/10.13182/NSE90-A23720
Influence of Water Density Change on the Criticality in Special Fuel Lattices
János Gadó, István Vidovszky
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 217-221
Technical Paper | doi.org/10.13182/NSE90-A23721
A Diffusion Iterative Model for Simulation of Reactivity Devices in Pressurized Heavy Water Reactors
V. Jagannathan, R. P. Jain, Vinod Kumar, H. C. Gupta, P. D. Krishnani
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 222-238
Technical Paper | doi.org/10.13182/NSE90-A23722
Neutron Energy Spectra in Lithium: Measurements and Calculations
R. Ofek, A. Tsechanski, A. Goldfeld, G. Shani, A. E. Profio, J. J. Wagschal
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 239-257
Technical Paper | doi.org/10.13182/NSE90-A23723
Neutron Absorption Cross Section of 236U
R. L. Macklin, C. W. Alexander
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 258-270
Technical Paper | doi.org/10.13182/NSE90-A23724
Activation Cross Sections of Neutron Threshold Reactions on Some Zirconium Isotopes in the 5.4- to 10.6-MeV Energy Range
M. Ibn Majah, S. M. Qaim
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 271-276
Technical Paper | doi.org/10.13182/NSE90-A23725
Fast Neutron Capture Cross Sections of Europium
Xiang Zhengyu, Xu Haishan, Li Yexiang, Mu Yunshan, Wang Shiming, Liu Jianfeng
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 277-279
Technical Paper | doi.org/10.13182/NSE90-A23726
Systematics and Parameterization of Continuum Angular Distributions for Application to Reactions Induced by 14-MeV Neutrons
Isao Kumabe, Yukinobu Watanabe, Yoshimitsu Nohtomi, Mitsuru Hanada
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 280-287
Technical Paper | doi.org/10.13182/NSE90-A23727
On the Calculation of Steam Explosion Conversion Ratios from Experimental Data
Y. M. Farawila, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 288-295
Technical Note | doi.org/10.13182/NSE90-A23728
Studies on the Higher Order Spatial Difference Schemes at the Interface of Two Media
V. Sundararaman
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 296-299
Technical Note | doi.org/10.13182/NSE90-A23729
A Neutron Multiplicity Counter for Plutonium Assay
N. Dytlewski, N. Ensslin, J. W. Boldeman
Nuclear Science and Engineering | Volume 104 | Number 4 | April 1990 | Pages 301-313
Technical Paper | doi.org/10.13182/NSE90-A23731
Dynamic Subcriticality Measurements Using the 252Cf-Source-Driven Noise Analysis Method
J. T. Mihalczo, E. D. Blakeman, G. E. Ragan, E. B. Johnson, Y. Hachiya
Nuclear Science and Engineering | Volume 104 | Number 4 | April 1990 | Pages 314-338
Technical Paper | doi.org/10.13182/NSE90-A23732
Neutron Yields from Stopping- and Near-Stopping-Length Targets for 256-MeV Protons
M. M. Meier, C. A. Goulding, G. L. Morgan, J. L. Ullmann
Nuclear Science and Engineering | Volume 104 | Number 4 | April 1990 | Pages 339-363
Technical Paper | doi.org/10.13182/NSE90-A23733
A Novel Fusion Power Concept Based on Molten-Salt Technology: PACER Revisited
Charles J. Call, Ralph W. Moir
Nuclear Science and Engineering | Volume 104 | Number 4 | April 1990 | Pages 364-373
Technical Paper | doi.org/10.13182/NSE90-A23734
A Quasi-Deterministic Approximation of the Monte Carlo Importance Function
Thomas E. Booth
Nuclear Science and Engineering | Volume 104 | Number 4 | April 1990 | Pages 374-384
Technical Paper | doi.org/10.13182/NSE90-A23735
The Coarse Space-Energy Mesh Rebalancing Method for Neutron Diffusion Calculations in Fast Reactors
Yasuyoshi Kato, Hiroshi Urushihara
Nuclear Science and Engineering | Volume 104 | Number 4 | April 1990 | Pages 385-395
Technical Paper | doi.org/10.13182/NSE90-A23736
An Analytic Method for Analyzing Prompt-Critical Reactivity Transients
J. F. Carew
Nuclear Science and Engineering | Volume 104 | Number 4 | April 1990 | Pages 396-401
Technical Paper | doi.org/10.13182/NSE90-A23737
Spatial Mesh Effects on Three-Dimensional x-y-z Neutron Diffusion Calculations in Fast Breeder Reactors
Yasuyoshi Kato
Nuclear Science and Engineering | Volume 104 | Number 4 | April 1990 | Pages 402-411
Technical Note | doi.org/10.13182/NSE90-A23738
