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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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April 3–5, 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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Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
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Implications of Alternative Strategies for Transition to Sustainable Fuel Cycles
Antonino Romano, Thomas Boscher, Pavel Hejzlar, Mujid S. Kazimi, Neil E. Todreas
Nuclear Science and Engineering | Volume 154 | Number 1 | September 2006 | Pages 1-27
Technical Paper | doi.org/10.13182/NSE06-A2615
Mixed and Hybrid Finite Element Method for the Transport Equation
J. Cartier, G. Samba
Nuclear Science and Engineering | Volume 154 | Number 1 | September 2006 | Pages 28-47
Technical Paper | doi.org/10.13182/NSE06-A2616
Power Iteration Method for the Several Largest Eigenvalues and Eigenfunctions
Thomas E. Booth
Nuclear Science and Engineering | Volume 154 | Number 1 | September 2006 | Pages 48-62
Technical Paper | doi.org/10.13182/NSE05-05
Development of a Criticality Evaluation Method Involving the Granular Flow of the Nuclear Fuel in a Rotating Drum
Mikio Sakai, Kazuya Shibata, Seiichi Koshizuka
Nuclear Science and Engineering | Volume 154 | Number 1 | September 2006 | Pages 63-73
Technical Paper | doi.org/10.13182/NSE06-A2618
Development of Sweepout Model in APR1400 During an LBLOCA
Byoung-Uhn Bae, Yong-Soo Kim, Goon-Cherl Park
Nuclear Science and Engineering | Volume 154 | Number 1 | September 2006 | Pages 74-93
Technical Paper | doi.org/10.13182/NSE06-A2619
Critical Heat Flux of Subcooled Water Flow Boiling for High L/d Region
Koichi Hata, Masahiro Shiotsu, Nobuaki Noda
Nuclear Science and Engineering | Volume 154 | Number 1 | September 2006 | Pages 94-109
Technical Note | doi.org/10.13182/NSE06-A2620
A Method for Fast Determination of the Parameter in Nuclear Reactors
I. M. Cohen, M. Arrondo, M. A. Arribére, M. C. Fornaciari Iljadica
Nuclear Science and Engineering | Volume 154 | Number 1 | September 2006 | Pages 110-117
Technical Note | doi.org/10.13182/NSE06-A2621
Analysis of Sample Irradiation Experiments in Phénix for JEFF-3.0 Nuclear Data Validation
J. Tommasi, E. Dupont, P. Marimbeau
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 119-133
Technical Paper | doi.org/10.13182/NSE154-119
The Search for Superconvergence in Spherical Harmonics Approximations
Alain Hébert
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 134-173
Technical Paper | doi.org/10.13182/NSE06-A2623
Temporal Accuracy of the Nonequilibrium Radiation Diffusion Equations Applied to Two-Dimensional Multimaterial Simulations
Vincent A. Mousseau, Dana A. Knoll
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 174-189
Technical Paper | doi.org/10.13182/NSE06-A2624
Continuous-Energy Multidimensional SN Transport for Problem-Dependent Resonance Self-Shielding Calculations
Zhaopeng Zhong, Thomas J. Downar, Yunlin Xu, Mark L. Williams, Mark D. DeHart
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 190-201
Technical Paper | doi.org/10.13182/NSE06-3
Proton Source Efficiency for Heterogeneous Distribution of Actinides in the Core of an Accelerator-Driven System
Per Seltborg, Jan Wallenius
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 202-214
Technical Paper | doi.org/10.13182/NSE06-A2626
Compton Current Generated by Nuclear Radiation: A Coupled Neutron-Gamma-Electron Transport Model
Gundra Kondayya, Aditi Ray
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 215-222
Technical Paper | doi.org/10.13182/NSE06-A2627
Oxygen Control Technique in Molten Lead and Lead-Bismuth Eutectic Systems
Jinsuo Zhang, Ning Li, Yitung Chen
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 223-232
Technical Paper | doi.org/10.13182/NSE06-A2628
Lead- and Bismuth-Borate Fly-Ash Glasses as Gamma-Ray-Shielding Materials
Kulwant Singh, Ashutosh Goel, Shaweta Mohan, Annu Arora, Gopi Sharma
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 233-240
Technical Paper | doi.org/10.13182/NSE06-A2629
A Data Identification Method for the Improvement of a Cross-Section Model
Aldo Dall'Osso
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 241-246
Technical Paper | doi.org/10.13182/NSE06-A2630
A General Method of Conserving Mass in Complex Geometry Simulations on Mesh Grids and Its Implementation in BOT3P5.0
Roberto Orsi
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 247-259
Computer Code Abstract | doi.org/10.13182/NSE06-A2631
Neutron Capture and Total Cross-Section Measurements and Resonance Parameters of Gadolinium
G. Leinweber, D. P. Barry, M. J. Trbovich, J. A. Burke, N. J. Drindak, H. D. Knox, R. V. Ballad, R. C. Block, Y. Danon, L. I. Severnyak
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 261-279
Technical Paper | doi.org/10.13182/NSE05-64
Modeling and Neutron-Induced Fission Cross Sections for Americium
D. Rochman, M. Herman, P. Oblozinský, M. Sin
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 280-293
Technical Paper | doi.org/10.13182/NSE06-A2633
Neutron Capture and Transmission Measurements and Resonance Parameter Analysis of Niobium
N. J. Drindak, J. A. Burke, G. Leinweber, J. A. Helm, J. G. Hoole, R. C. Block, Y. Danon, R. E. Slovacek, B. E. Moretti, C. J. Werner, M. E. Overberg, S. A. Kolda, M. J. Trbovich, D. P. Barry
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 294-301
Technical Paper | doi.org/10.13182/NSE06-A2634
A Study of Nonlinear Oscillation and Limit Cycles in Boiling Water Reactors - I: The Global Mode
Yousef M. Farawila, Douglas W. Pruitt
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 302-315
Technical Paper | doi.org/10.13182/NSE06-A2635
A Study of Nonlinear Oscillation and Limit Cycles in Boiling Water Reactors - II: The Regional Mode
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 316-327
Technical Paper | doi.org/10.13182/NSE06-A2636
Homogenization Method for the Two-Dimensional Low-Order Quasi-Diffusion Equations for Reactor Core Calculations
Hikaru Hiruta, Dmitriy Y. Anistratov
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 328-352
Technical Paper | doi.org/10.13182/NSE06-A2637
Design of a Model Predictive Power Controller for an SP-100 Space Reactor
Man Gyun Na, Belle R. Upadhyaya, Xiaojia Xu, In Joon Hwang
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 353-366
Technical Paper | doi.org/10.13182/NSE06-A2638
Neutron Slowing Down in a Detector with Absorption
Sara A. Pozzi, Imre Pázsit
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 367-373
Technical Paper | doi.org/10.13182/NSE06-A2639
Analysis of the Nuclear Level-Density Parameters of Some Large Deformed Odd-A and Odd-Odd Nuclei in the Region of Rare Earth Elements
Seref Okuducu, Erhan Eser, Savas Sönmezoglu
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 374-381
Technical Paper | doi.org/10.13182/NSE06-A2640
