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Division Spotlight
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.
Meeting Spotlight
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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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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Acceptable Seismic-Induced Risks per U.S. Department of Energy Standards at Nuclear Facilities
James J. Dahl, Shivi Singh, Marvin G. Zimmerman
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 1-17
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A14515
Development of Erbia-Credit Super-High-Burnup Fuel: Evaluation of Minimum Erbia Content for Criticality Safety Analyses
Masatoshi Yamasaki, Hironobu Unesaki, Akio Yamamoto, Toshikazu Takeda, Masaaki Mori
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 18-27
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14516
Characterizing Limited-Separations Fuel Cycles Using Breed-and-Burn Reactors
Robert Petroski, Benoit Forget, Charles Forsberg
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 28-45
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14517
Fuzzy Evaluation of Horizontal Nuclear Proliferation Risk for More Efficient Resource Allocation of IAEA's Integrated Safeguards
Naoto Otsuka
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 46-64
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14518
Determination Procedures of High Risk Zones for Local Wall Thinning Due to Flow-Accelerated Corrosion
Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Hiroaki Suzuki, Soji Koikari, Seiichi Koshizuka, Derek H. Lister
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 65-77
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A14519
Nonhomogeneous-Nonequilibrium Two-Phase-Flow Model for Nuclear Reactor Single-Channel Stability Analysis
Jiyun Zhao, C. P. Tso, K. J. Tseng
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 78-88
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A14520
Development of CAD-MCNP Interface Program GEOMIT and Its Applicability for ITER Neutronics Design Calculations
Hesham R. Nasif, Fukuzo Masuda, Hidetsugu Morota, Hitomasa Iida, Satoshi Sato, Chikara Konno
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 89-102
Technical Paper | Radiation Protection | doi.org/10.13182/NT12-A14521
The Behavior of Radiolytically Produced Hydrogen in a High-Level Liquid Waste Tank of a Reprocessing Plant: Hydrogen Concentration Under Gamma Irradiation of the Simulated Solution
Takashi Kodama, Masanao Nakano, Kunio Fujita, Shingo Matsuoka, Yasuo Ito, Chihiro Matsuura, Hirotsugu Shiraishi, Yousuke Katsumura
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 103-110
Technical Paper | Reprocessing | doi.org/10.13182/NT11-45
Technology and Policy Aspects of Deep Borehole Nuclear Waste Disposal
M. J. Driscoll, R. K. Lester, K. G. Jensen, B. W. Arnold, P. N. Swift, P. V. Brady
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 111-121
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT12-A14523
Development of a U.S. Nuclear Waste Repository Research Program in Salt
Bruce A. Robinson, Ned Z. Elkins, Joe T. Carter
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 122-138
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT12-A14524
A New Analysis of Composite Materials for Use in Glove-Box Applications
Adam Davis, Donald J. Dudziak
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 139-148
Technical Note | Materials for Nuclear Systems | doi.org/10.13182/NT12-A14525
Coating Parameters That Influence the Defect Ratio of TRISO Coated Fuel Particles
Jacobus J. Hancke, John C. Barry, Gerrit T. Van Rooyen, Johan P. R. De Villiers
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 149-158
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A14630
Pressure Drop in a Pebble Bed Reactor Under High Reynolds Number
Yassin A. Hassan, Changwoo Kang
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 159-173
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A14631
Demonstration of Implicit Coupling of TRACE/PARCS Using Simplified One-Dimensional Problems
Justin K. Watson, Kostadin N. Ivanov
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 174-190
Technical Paper | Reactor Safety | doi.org/10.13182/NT12-A14632
Coupling the Back End of Fuel Cycles with Repositories
Charles Forsberg
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 191-204
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14633
Study of Fukushima Daiichi Nuclear Power Station Unit 4 Spent-Fuel Pool
Dean Wang, Ian C. Gauld, Graydon L. Yoder, Larry J. Ott, George F. Flanagan, Matthew W. Francis, Emilian L. Popov, Juan J. Carbajo, Prashant K. Jain, John C. Wagner, Jess C. Gehin
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 205-215
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT12-A14634
Experiment Optimization to Reduce Nuclear Data Uncertainties in Support of Reactor Design
Tracy E. Stover, Paul J. Turinsky
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 216-230
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT12-A14635
Reconstruction Algorithms for Directional Neutron Detection Using a Time Projection Chamber
C. Roecker, N. S. Bowden, G. Carosi, M. Heffner, I. Jovanovic
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 231-240
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT12-A14636
The European Lead-Cooled EFIT Plant: An Industrial-Scale Accelerator-Driven System for Minor Actinide Transmutation—I
L. Mansani, C. Artioli, M. Schikorr, G. Rimpault, C. Angulo, D. De Bruyn
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 241-263
Technical Paper | Accelerators | doi.org/10.13182/NT11-96
Description of the European Helium-Cooled EFIT Plant: An Industrial-Scale Accelerator-Driven System for Minor Actinide Transmutation—II
Jean-François Pignatel, Pierre Richard, Gerald Rimpault, Julian Murgatroyd, Richard Stainsby, Michael Schikorr, Evaldas Bubelis, Sophie Larmignat, Antony Woaye Hune, Danas Ridikas, Alan Takibayev
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 264-296
Technical Paper | Accelerators | doi.org/10.13182/NT11-97
Initial MCNP6 Release Overview
T. Goorley, M. James, T. Booth, F. Brown, J. Bull, L. J. Cox, J. Durkee, J. Elson, M. Fensin, R. A. Forster, J. Hendricks, H. G. Hughes, R. Johns, B. Kiedrowski, R. Martz, S. Mashnik, G. McKinney, D. Pelowitz, R. Prael, J. Sweezy, L. Waters, T. Wilcox, T. Zukaitis
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 298-315
Technical Paper | Special Issue on the Initial Release of MCNP6 / Radiation Transport and Protection | doi.org/10.13182/NT11-135
MCNP6 Unstructured Mesh Initial Validation and Performance Results
Roger L. Martz
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 316-335
Technical Paper | Special Issue on the Initial Release of MCNP6 / Radiation Transport and Protection | doi.org/10.13182/NT12-A15347
The MCNP6 Delayed-Particle Feature
Joe W. Durkee, Jr., Michael R. James, Gregg W. McKinney, Laurie S. Waters, Tim Goorley
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 336-354
Technical Paper | Special Issue on the Initial Release of MCNP6 / Radiation Transport and Protection | doi.org/10.13182/NT12-22
MCNP Variance Reduction Developments in the 21st Century
Thomas E. Booth, R. Arthur Forster, Roger L. Martz
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 355-371
Technical Paper | Special Issue on the Initial Release of MCNP6 / Radiation Transport and Protection | doi.org/10.13182/NT12-A15349
Hybrid Monte Carlo-Deterministic Methods for Reactor Analysis
Zeyun Wu, Qiong Zhang, Hany Abdel-Khalik
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 372-382
Technical Paper | Special Issue on the Initial Release of MCNP6 / Fission Reactors | doi.org/10.13182/NT12-A15350
Sensitivity and Uncertainty of OECD Benchmark Ringhals-1 TRACE/PARCS Stability Prediction
Ivan Gajev, Tomasz Kozlowski, Yunlin Xu, Thomas Downar
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 383-398
Technical Paper | Special Issue on the Initial Release of MCNP6 / Fission Reactors | doi.org/10.13182/NT12-A15351
Construction and Analysis of a Dynamic Model for a Canadian Direct-Cycle SCWR for Control System Studies
Peiwei Sun, Jin Jiang
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 399-421
Technical Paper | Special Issue on the Initial Release of MCNP6 / Thermal Hydraulics | doi.org/10.13182/NT12-A15352
Advanced Multieffect Distillation System for Desalination Using Waste Heat from Gas Brayton Cycles
Haihua Zhao, Per F. Peterson
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 422-436
Technical Paper | Special Issue on the Initial Release of MCNP6 / Thermal Hydraulics | doi.org/10.13182/NT12-A15353
Lightbridge Corporation's Advanced Metallic Fuel for Light Water Reactors
James Malone, Aaron Totemeier, Norton Shapiro, Swaminathan Vaidyanathan
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 437-442
Technical Paper | Special Issue on the Initial Release of MCNP6 / Materials for Nuclear Systems | doi.org/10.13182/NT12-A15354
International Database on Reactor Pressure Vessel Materials for Long-Term Operation of NPPs
A. Kryukov, A. Ballesteros, C. Bruynooghe, U. Von Estorff
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 443-449
Technical Paper | Special Issue on the Initial Release of MCNP6 / Materials for Nuclear Systems | doi.org/10.13182/NT12-A15355
Effects of Gamma Irradiation on Adhesion of Polymer Microstructure-Based Dry Adhesives
Paul Day, Mark Cutkosky, Anastasia McLaughlin
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 450-455
Technical Note | Special Issue on the Initial Release of MCNP6 / Radioisotopes | doi.org/10.13182/NT12-A15356
