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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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Development of an Advanced Core Analysis System for Boiling Water Reactor Designs
Hiromi Maruyama, Junichi Koyama, Motoo Aoyama, Kazuya Ishii, Atsushi Zukeran, Takashi Kiguchi, Akira Nishimura
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 3-13
Technical Paper | Kiyose Birthday Anniversary Special / Fission Reactor | doi.org/10.13182/NT97-A35351
Feasibility Studies on Plutonium and Minor Actinide Burning in Fast Reactors
Toshio Wakabayashi, Katsuro Takahashi, Tsutomu Yanagisawa
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 14-25
Technical Paper | Kiyose Birthday Anniversary Special / Nuclear Fuel Cycle | doi.org/10.13182/NT118-14
Applications of Genetic Algorithms to Optimization Problems in the Solvent Extraction Process for Spent Nuclear Fuel
Ryota Omori, Yasushi Sakakibara, Atsuyuki Suzuki
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 26-31
Technical Paper | Kiyose Birthday Anniversary Special / Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35353
Finite Time Settling Control of Pulsed Columns
Hidematsu Ikeda, Naotake Katoh
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 32-41
Technical Paper | Kiyose Birthday Anniversary Special / Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35354
Separation and Coprecipitation of Lanthanides and Americium by Photolysis
Satoru Tsushima, Shinya Nagasaki, Atsuyuki Suzuki
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 42-48
Technical Paper | Kiyose Birthday Anniversary Special / Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35355
Geochemical Properties of Bentonite Pore Water in High-Level-Waste Repository Condition
Toshiaki Ohe, Masaki Tsukamoto
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 49-57
Technical Paper | Kiyose Birthday Anniversary Special / Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35356
Impact of Colloid Generation on Actinide Migration in High-Level Radioactive Waste Disposal: Overview and Laboratory Analysis
Satoru Tanaka, Shinya Nagasaki
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 58-68
Technical Paper | Kiyose Birthday Anniversary Special / Radioactive Waste Management | doi.org/10.13182/NT97-A35357
Critical Experiments on 10% Enriched Uranyl Nitrate Solution Using A 60-cm-Diameter Cylindrical Core
Yoshinori Miyoshi, Takuya Umano, Kotaro Tonoike, Naoki Izawa, Susumu Sugikawa, Shuji Okazaki
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 69-82
Technical Paper | Kiyose Birthday Anniversary Special / Nuclear Criticality Safety | doi.org/10.13182/NT97-A35358
Seismic Test of a Heat Exchanger With a Helically Coiled Tube Bundle
Masatoshi Futakawa, Hideki Takumi, Shoji Takada, Yoshiaki Miyamoto
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 83-88
Technical Paper | Kiyose Birthday Anniversary Special / Fission Reactor | doi.org/10.13182/NT97-A35359
Advanced Vessel Cooling System Concept for High-Temperature Gas-Cooled Reactors
Akio Saikusa, Kazuhiko Kunitomi, Shusaku Shiozawa
Nuclear Technology | Volume 118 | Number 2 | May 1997 | Pages 89-96
Technical Paper | Fission Reactor | doi.org/10.13182/NT97-A35370
A Decision Support System for Emergency Response to Major Nuclear Accidents
Ioannis A. Papazoglou, Michalis D. Christou
Nuclear Technology | Volume 118 | Number 2 | May 1997 | Pages 97-122
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35371
An Investigation of Cesium Release from Coated Particle Fuel of the High-Temperature Gas-Cooled Reactor
Kazuhiro Sawa, Kazuo Minato, Tsutomu Tobita, Kousaka Fukuda
Nuclear Technology | Volume 118 | Number 2 | May 1997 | Pages 123-131
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35372
Stochastic Radionuclide Distributions After a Basaltic Eruption for Performance Assessments of Yucca Mountain
Mark S. Jarzemba
Nuclear Technology | Volume 118 | Number 2 | May 1997 | Pages 132-141
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35373
Comparison of Characteristics of Solution and Conventional Reactors for 99Mo Production
Dan Glenn, A. Sharif Heger, William B. Hladik III
Nuclear Technology | Volume 118 | Number 2 | May 1997 | Pages 142-150
Technical Paper | Radioisotopes and Isotopes | doi.org/10.13182/NT97-A35374
A Two-Phase Flow Regime Map for a Maple-Type Nuclear Research Reactor Fuel Channel: Effect of Hexagonal Finned Bundle
Glenn D. Harvel, J. S. Chang, V. Santhana Krishnan
Nuclear Technology | Volume 118 | Number 2 | May 1997 | Pages 151-161
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35375
Simulation of a Small Cold-Leg-Break Experiment at the PMK-2 Test Facility Using the RELAP5 and ATHLET Codes
György Ézsöl, Atilla Guba, László Perneczky, Eckhard Krepper, Horst-Michael Prasser, Frank Schäfer
Nuclear Technology | Volume 118 | Number 2 | May 1997 | Pages 162-174
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35376
Three-Dimensional Numerical Simulations of Heat Transfer in an Annular Fuel Channel with Periodic Spacer Ribs Under a Fully Developed Turbulent Flow
Kazuyuki Takase
Nuclear Technology | Volume 118 | Number 2 | May 1997 | Pages 175-185
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35377
Wind-Field Modeling of Nuclear Accident Consequences for Hong Kong
Mankit Ray Yeung, Wai Sing Lui
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 187-199
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35361
Chemical-Physical Behavior of Light Water Reactor Core Components Tested Under Severe Reactor Accident Conditions in the CORA Facility
Peter Hofmann, Siegfried J. L. Hagen, Volker Noack, Gerhard Schanz, Leo K. Sepold
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 200-224
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT118-200
Dissolution Kinetics of U3Si2 Particles in Alkaline Hydrogen Peroxide
Bruce A. Buchholz, Joseph C. Hutter, George F. Vandegrift
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 225-232
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35363
Diffusion Paths of Cesium in Water-Saturated Mortar
Kazuya Idemitsu, Ken-ichiro Kuwata, Hirotaka Furuya, Yaohiro Inagaki, Tatsumi Arima
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 233-241
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT97-A35364
Void Fraction Measurements in Nuclear Reactors Via Neutron Noise Methods
Robert Kozma, Masaharu Kitamura, J. Eduard Hoogenboom
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 242-253
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35365
Hierarchical Fuzzy Logic Water-Level Control in Advanced Boiling Water Reactors
Chaung Lin, Feng-Ling Jeng, Chi-Szu Lee, Raghu Raghavan
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 254-263
Technical Paper | Reactor Operation | doi.org/10.13182/NT97-A35366
A Correlation-Based Signal Validation Method for Fixed In-Core Detectors
Ferenc Adorján, Toshio Morita
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 264-275
Technical Paper | Reactor Control | doi.org/10.13182/NT97-A35367
