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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Jun 2025
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Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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Feasibility Study of a Proliferation-Resistant Fuel Form for Plutonium Recycling
Sukesh K. Aghara, Carl A. Beard
Nuclear Technology | Volume 137 | Number 1 | January 2002 | Pages 1-9
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3253
IIST and BETHSY Counterpart Tests on a PWR Total Loss-of-Feedwater Transient with Two Different Bleed-and-Feed Scenarios
Tay-Jian Liu
Nuclear Technology | Volume 137 | Number 1 | January 2002 | Pages 10-27
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3254
Percolation Cooling of the Three Mile Island Unit 2 Lower Head by Way of Thermal Cracking and Gap Formation
K. L. Thomsen
Nuclear Technology | Volume 137 | Number 1 | January 2002 | Pages 28-46
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3255
Transmutation of 129I Using an Accelerator-Driven System
Kenji Nishihara, Hideki Takano
Nuclear Technology | Volume 137 | Number 1 | January 2002 | Pages 47-59
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3256
Structure and Properties of Chromium- and Zinc-Oxide Layers Formed on Zircaloy-2 in High-Temperature Water
Orlin L. Blajiev, Chihiro Matsuura, Daisuke Hiroishi, Kenkichi Ishigure
Nuclear Technology | Volume 137 | Number 1 | January 2002 | Pages 60-71
Technical Paper | Radioisotopes | doi.org/10.13182/NT02-A3257
High Local Power Densities Permissible at Siemens Pressurized Water Reactors
Klaus Kuehnel, Klaus-Deiter Richter, Gerhard Drescher, Ivo Endrizzi
Nuclear Technology | Volume 137 | Number 2 | February 2002 | Pages 73-83
Technical Paper | Fission Reactors | doi.org/10.13182/NT02-A3258
Fast Burner Reactor Devoted to Minor Actinide Incineration
Nadia Messaoudi, Jean Tommasi
Nuclear Technology | Volume 137 | Number 2 | February 2002 | Pages 84-96
Technical Paper | Fission Reactors | doi.org/10.13182/NT02-A3259
Reactivity, Isotopic, and Thermal Steady-State Analysis of Homogeneous Thoria-Urania Fuel
Eric P. Loewen, Kevan D. Weaver, Judith K. Hohorst
Nuclear Technology | Volume 137 | Number 2 | February 2002 | Pages 97-110
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3260
Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels
Yoshinori Nakahara, Kenya Suyama, Jun Inagawa, Ryuji Nagaishi, Setsumi Kurosawa, Nobuaki Kohno, Mamoru Onuki, Hiroki Mochizuki
Nuclear Technology | Volume 137 | Number 2 | February 2002 | Pages 111-126
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-2
H Control Theory Applied to Xenon Control for Load-Following Operation of a Nuclear Reactor
Sung Goo Chi, Nam Zin Cho
Nuclear Technology | Volume 137 | Number 2 | February 2002 | Pages 127-138
Technical Paper | Nuclear Plany Operations and Control | doi.org/10.13182/NT00-31
Removal of Metal-Oxide Layers Formed on Stainless and Carbon Steel Surfaces by Excimer Laser Irradiation in Various Atmospheres
Yutaka Kameo, Mikio Nakashima, Takakuni Hirabayashi
Nuclear Technology | Volume 137 | Number 2 | February 2002 | Pages 139-146
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT02-A3263
An Optimization Scheme for High-Level-Waste Removal Sequencing Using ProdMod
Pran K. Paul, Michael V. Gregory, Tunc Aldemir
Nuclear Technology | Volume 137 | Number 2 | February 2002 | Pages 147-162
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3264
Application of Autoregressive Models to In-Service Estimation of Transient Response for LMFBR Process Instrumentation
Masashi Ueda, Katsuma Tomobe, Keiichi Setoguchi, Akira Endou
Nuclear Technology | Volume 137 | Number 2 | February 2002 | Pages 163-168
Technical Note | Materials | doi.org/10.13182/NT02-A3265
Monte Carlo Simulation of the TRIGA Mark II Benchmark Experiment with Burned Fuel
Robert Jeraj, Tomaz Zagar, Matjaz Ravnik
Nuclear Technology | Volume 137 | Number 3 | March 2002 | Pages 169-180
Technical Paper | Fission Reactors | doi.org/10.13182/NT02-A3266
Iodine Behavior Under Conditions Relating to Nuclear Reactor Accidents
Fariborz Taghipour, Greg J. Evans
Nuclear Technology | Volume 137 | Number 3 | March 2002 | Pages 181-193
Technical Paper | Reactor Safety | doi.org/10.13182/NT02-A3267
Simulation of Free-Surface Flows with Heat Transfer and Phase Transitions and Application to Corium Spreading in the EPR
Ralf Wittmaack
Nuclear Technology | Volume 137 | Number 3 | March 2002 | Pages 194-212
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3268
A New Assessment of RELAP5-3D Using a General Electric Level Swell Problem
David L. Aumiller, Edward T. Tomlinson, William G. Clarke
Nuclear Technology | Volume 137 | Number 3 | March 2002 | Pages 213-227
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT137-213
A Reactive Transport Model for Oxidative Dissolution of Spent Fuel and Release of Nuclides Within a Defective Canister
Longcheng Liu, Ivars Neretnieks
Nuclear Technology | Volume 137 | Number 3 | March 2002 | Pages 228-240
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3270
Thermohydrological Effects on a Nonreactive Aqueous Species in Unsaturated Fractured Geologic Materials
David W. Esh, Barry E. Scheetz
Nuclear Technology | Volume 137 | Number 3 | March 2002 | Pages 241-251
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3271
Impact of the Nuclear Option on the Environment and the Economy
Upendra S. Rohatgi, Jae H. Jo, John C. Lee, Robert A. Bari
Nuclear Technology | Volume 137 | Number 3 | March 2002 | Pages 252-264
Technical Paper | Environmental Science, Technology, and Effects | doi.org/10.13182/NT02-A3272
