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The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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ANS Student Conference 2025
April 3–5, 2025
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Nuclear Science and Engineering
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Nuclear Technology
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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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The Current Status of Theoretically Based Approaches to the Prediction of the Critical Heat Flux in Flow Boiling
Joel Weisman
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 1-21
Critical Review | doi.org/10.13182/NT92-A34699
Basic Philosophy of the Safety Design of the Toshiba Boiling Water Reactor
Takashi Sato
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 22-35
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34700
Use of Artificial Neural Networks to Analyze Nuclear Power Plant Performance
Zhichao Guo, Robert E. Uhrig
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 36-42
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34701
Containment Pressurization and Burning of Combustible Gases in a Large, Dry PWR Containment During a Station Blackout Sequence
Min Lee, Chen Tsung Fan
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 43-57
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34702
Delayed Neutron Noise Characteristics of an In-Pile Fission Product Loop
Tetsuo Tamaoki, Takuhiko Sakai, Hiroshi Endo, Kazuo Haga, Ryoichi Takahashi
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 58-69
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34703
The Iodine Species and Their Behavior in the Dissolution of Spent-Fuel Specimens
Tsutomu Sakurai, Akira Takahashi, Niroh Ishikawa, Yoshihide Komaki, Mamoru Ohnuki, Takeo Adachi
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 70-79
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT92-A34704
A Model for Sound Velocity in a Two-Phase Air-Water Bubbly Flow
Nien-Mien Chung, Wei-Keng Lin, Bau-Shei Pei, Yih-Yun Hsu
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 80-89
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34705
Thermal-Hydraulic Characteristics of Coolant in the Core Bottom Structure of the High-Temperature Engineering Test Reactor
Yoshiyuki Inagaki, Kazuhiko Kunitomi, Yoshiaki Miyamoto, Ikuo Ioka, Kunihiko Suzuki
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 90-103
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34706
Study of Void Fraction and Mixing of Immiscible Liquids in a Pool Configuration by an Upward Gas Flow
Joan-Carles Casas, Michael L. Corradini
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 104-119
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34707
An Integrated Operator Decision Aid System for Boiling Water Reactor Power Plants
Shigeki Fukutomi, Norio Naito, Yoji Takizawa
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 120-132
Technical Paper | Reactor Operation | doi.org/10.13182/NT92-A34708
A Study of Thermal-Hydraulic Requirements for Increasing the Power Rates for Natural-Circulation Boiling Water Reactors
Akira Yasuo, Fumio Inada, Masataka Hidaka
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 135-141
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34684
The Use of Influence Diagrams for Evaluating Severe Accident Management Strategies
Moosung Jae, George E. Apostolakis
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 142-157
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34685
Seismic Study of High-Temperature Engineering Test Reactor Core Graphite Structures
Tatsuo Iyoku, Yoshiyuki Inagaki, Shusaku Shiozawa, Isoharu Nishiguchi
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 158-168
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34686
Seismic Response of the High-Temperature Engineering Test Reactor Core Bottom Structure
Tatsuo Iyoku, Yoshiyuki Inagaki, Shusaku Shiozawa, Masatoshi Futakawa, Toshiyo Miki
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 169-176
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34687
COBRA/RELAP5: A Merged Version of the COBRA-TF and RELAP5/MOD3 Codes
Sang Yong Lee, Jae Jun Jeong, Si-Hwan Kim, Soon Heung Chang
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 177-187
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT99-177
Manned Mars Rover Powered by a Nuclear Reactor: Radiation Shield Analysis
Nicholas J. Morley, Mohamed S. El-Genk
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 188-202
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34689
MELCOR Modeling of the National Research Universal Full-Length High-Temperature 2 Experiment
Imtiaz K. Madni, Xiao-Dong Guo
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 203-212
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34690
Determination of Low Activities Released by a Decommissioned Fuel Fabrication Plant Through Natural Air Exchange
Bernd Sohnius, Rudolf Anton, Erwin Wehner, Frank-Dietrich Heidt, Rudolf Rabenstein
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 213-221
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34691
Benchmark of CASMO-3/ SIMULATE-3 with a New Modeling for the Chinshan and Kuosheng Boiling Water Reactors
Pin-Wu Kao, Jing-Tong Yang, Chian-Yeh Ho, Cheng-Hsien Chou, Ruey-Chang Huang, and, Ta-Chieh Sun
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 222-234
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34692
Destruction of Emulsions Stabilized by Precipitates of Zirconium and Tributyl Phosphate Degradation Products
Hiroshi Sugai, Kenzo Munakata
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 235-241
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT92-A34693
Corrosion Behavior of Silicon Nitride, Magnesium Oxide, and Several Metals in Molten Calcium Chloride with Chlorine
David F. Mclaughlin, Charles E. Sessions, John E. Marra
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 242-251
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT92-A34694
Detection of Parts-Per-Million Levels of Hydrogen in Solids Using a Modified Notched Neutron Spectrum Technique
William H. Miller, Li-Te Lin, Robert M. Brugger, Walter Meyer
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 252-257
Technical Paper | Material | doi.org/10.13182/NT92-A34695
A Model for Sound Velocity and Its Relationship with Interfacial Area in a Steam-Water, Two-Phase Bubbly Flow
Nien-Mien Chung, Wei-Keng Lin, Bau-Shei Pei, Dong-Jye Li, Yih-Yun Hsu†
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 258-267
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34696
Numerical Solution for the Nonlinear Diffusion Equation Describing the Transport of Volatile Fission Products in Nuclear Fuels
Conor O’Carroll, Klaus Lassmann
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 268-273
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34697
Results of an Investigation of Safety Improvement and Service Life Prolongation of the BOR-60 Experimental Reactor
Vladimir N. Efimov, Gadzhy I. Gadzhiev, Arcady A. Minakov
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 275-279
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34711
Power Instability and Stochastic Dynamics of Periodic Pulsed Reactors
Evgueny P. Shabalin
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 280-288
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34712
The In-Pile Local Blockage Experiments Mol-7C/6 and 7 — Results and Preliminary Interpretation
Karl Schleisiek, Jürgen Aberle, Siegfried Jacobi, August Rahn, Lothar Schmidt, Gilbert Vanmassenhove, Alfons Verwimp
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 289-300
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34713
QUASAR — A Computer Code for Analyzing Subassembly Accidents in Liquid-Metal Fast Breeder Reactors
Fumio Kasahara, Hiroshi Endo
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 301-308
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34714
Freezing Phenomena of Ceramic Alumina Melts Flowing in Pin Bundles
Günter Fieg, Manfred Möschke, Heinrich Werle
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 309-317
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34715
Passive Safety Features of a Bottom-Supported Fast Breeder Reactor Vessel
Hiroshi Endo, Yoshio Kumaoka, Simcha Golan, Hiroshi Nakagawa
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 318-329
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34716
Release Kinetics of Volatile Fission Products Under Severe Accident Conditions
Brent J. Lewis, Fernando C. Iglesias, C. E. Laurence Hunt, David S. Cox
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 330-342
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34717
Quantitative Studies of Severe Fuel Damage Using Delayed Neutron Data
Theodore H. Bauer, Thomas H. Braid, Karl Schleisiek
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 343-350
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34718
A Computer Model for Predicting Transient Fission Gas Release from UO2 Fuel
Ki-Seob Sim, Ho Chun Suk, Young Ku Yoon
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 351-365
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34719
The Advanced Fluid Dynamics Model Program: Scope and Accomplishment
William R. Bohl, Dirk Wilhelm
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 366-373
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34720
Thermohydraulic Model Experiments on the Transition from Forced to Natural Circulation for Pool-Type Fast Reactors
Helmut Hoffmann, Klaus Marten, Dietrich Weinberg, Hideki Kamide
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 374-385
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34721
Experiments on Convection Heat Transfer Along a Vertical Flat Plate Between Pools with Different Temperatures
Yoshiyuki Kataoka, Tohru Fukui, Shigeo Hatamiya, Toshitsugu Nakao, Masanori Naitoh, Isao Sumida
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 386-396
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34722
