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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Nuclear Technology
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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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Power Signal Validation for Taiwan Research Reactor
Chaung Lin, Jen-Min Chen, Shaw-Cuang Lee, Der-Jhy Shieh
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 7-13
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34191
Probabilistic Risk Assessment Based Inspection Guidance for Arkansas Nuclear One Unit 1
Truong V. Vo, Michael S. Harris, Bryan F. Gore
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 14-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34192
Applications of a Parallel Processing Modular Simulation System for Dynamic Simulation of Nuclear Power Plants
Hsing Chien Yeh, William E. Kastenberg, Walter J. Karplus
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 23-32
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34193
The Reflooding Phase After a Loss-of-Coolant Accident in an Advanced Pressurized Water Reactor
Marco Cigarini, Mario Dalle Donne
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 33-53
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34194
Testing of Electric Motors for Monitoring Age-Related Degradations
Mano Subudhi, John H. Taylor, Marvin Sheets
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 54-61
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34195
The Performance of High-Temperature Reactor Fuel Particles at Extreme Temperatures
Heinz Nabielek, Werner Schenk, Werner Heit, Alfred-Wilhelm Mehner, Daniel T. Goodin
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 62-81
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34196
Colloid Formation Study of U, Th, Ra, Pb, Po, Sr, Rb, and Cs in Briny (High Ionic Strength) Groundwaters: Analog Study for Waste Disposal
Tapas C. Maiti, MOnty R. Smith, Jagdish C. Laul
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 82-87
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34197
Inconsistencies in Thermodynamic Analyses of Long-Term Isolation of High-Level Waste
Donald G. Schweitzer
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 88-92
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34198
A Neutronic Study of an Accelerator-Based Neutron Irradiation Facility for Boron Neutron Capture Therapy
C.-K. Chris Wang, Thomas E. Blue, Reinhard Gahbauer
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 93-107
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT89-A34199
Experience with the On-Line Core Master Monitoring and Predicting System at Kernkraftwerk Leibstadt
Charles Jacquemart, Mabruk Methnani, Juan Jaliff, Sigurd Børresen
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 108-112
Technical Paper | Technique | doi.org/10.13182/NT89-A34200
Application of Magnetic Resonance Imaging to Visualization of Flow in Porous Media
Adolfas K. Gaigalas, Ann Chidester Van Orden, Baldwin Robertson, Thomas H. Mareci, Lori A. Lewis
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 113-118
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT89-A34201
Power Optimization of an Indirect Gas-Cooled Nuclear Reactor Plant
Chih Wu
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 123-127
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34182
Silver-Indium-Cadmium Control Rod Behavior in Severe Reactor Accidents
David A. Petti
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 128-151
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34183
Characterization of Suspended Particles in Three Mile Island Unit 2 Reactor Coolant Water
Kazuhiko Akamine, K. J. Hofstetter, V. F. Baston
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 152-168
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34184
Analysis of the Source Range Monitor During the First Four Hours of the Three Mile Island Unit 2 Accident
Horng-Yu Wu, Ming-Yuan Hsiao, Anthony J. Baratta, Bernard R. Bandini, E. L. Tolman
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 169-181
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34185
Oxidation Behavior of Spent UO2 Fuel
Todd K. Campbell, Edgar Robert Gilbert, Cheryl Knox Thornhill, Bernard J. Wrona
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 182-195
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34186
Trace Metal Characterization of the U-AI Matrix by Atomic Spectroscopy
A. A. Argekar, S. K. Thulasidas, M. J. Kulkarni, M. K. Bhide, R. Sampathkumar, S. V. Godbole, V. C. Adya, B. A. Dhawale, B. Rajeshwari, Neelam Goyal, P. J. Purohit, A. G. Page, A. G. I. Dalvi, T. R. Bangia, M. D. Sastry, P. R. Natarajan
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 196-204
Technical Paper | Analyse | doi.org/10.13182/NT89-A34187
Quality Assurance Verification of High-Flux Isotope Reactor Fuel Elements by the 252Cf-Source-Driven Noise Analysis Method
J. T. Mihalczo, W. T. King
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 205-223
Technical Paper | Techniques | doi.org/10.13182/NT88-2
Risk-Based Analysis Methods Applied to Nuclear Power Plant Technical Specifications
David P. Wagner, Larry A. Minton, John P. Gaertner
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 233-238
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34204
Analysis and Quantification of Common-Cause Failures on the Basis of Operating Experience
B. Thierry Meslin
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 239-246
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34205
Comparison Between Canadian Probabilistic Safety Assessment Methods Formulated by Atomic Energy of Canada Limited and Probabilistic Risk Assessment Methods
Hymie Sol Shapiro, James Edward Smith
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 247-251
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34206
Quantification of Dynamic Human Error Probabilities in Terms of Sampled Timing Data
Yean-Chuan Yeh, Jyh-Tong Teng
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 252-255
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34207
Overview of the Electric Power Research Institute Research Program on Common-Cause Failures
David H. Worledge, Ian B. Wall
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 256-259
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34208
A Modular Steady States Approach for Fuel Cycle Facility Probabilistic Risk Assessment
Hans J. Wingender, R. Leicht
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 260-264
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34209
Treating Data Uncertainties in Common-Cause Failure Analysis
Nathan Siu, Ali Mosleh
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 265-281
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34210
Probabilistic Risk Assessment Related to Multiple Ruptures of Steam Generator Tubes
Michel Bloch, Daniel Dussarté, Jean-Louis Pierrey
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 282-284
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34211
The GO-FLOW Methodology: A Reliability Analysis of the Emergency Core Cooling System of a Marine Reactor Under Accident Conditions
Takeshi Matsuoka, Michiyuki Kobayashi, Kazuo Takemura
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 285-295
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34212
The Use of Abnormal Event Data in Nuclear Power Reactor System Analysis Using the Sequence Combining Method
Henk W. Kalfsbeek
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 296-304
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34213
Seal Loss-of-Coolant Accident and Recovery Actions Following Loss of Component Cooling Water
Shih-Kuei Cheng
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 305-314
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34214
Use of Probabilistic Risk Assessment and Economic Risk at the Plant Design Stage: An Application
Selim Sancaktar, David R. Sharp
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 315-318
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34215
Lessons Learned from 21 Nuclear Plant Probabilistic Risk Assessments
B. John Garrick
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 319-330
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34216
Pancake Core High Conversion Light Water Reactor Concept
Yukio Ishiguro, Keisuke Okumura
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 331-343
Technical Paper | Probabilistic Safety Assessment and Risk Management / Fission Reactor | doi.org/10.13182/NT89-A34217
Four-Batch Fuel Management with Plutonium Recycling
Corinne Bangil, Gérard Gambier, Michel Soldevila
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 344-349
Technical Paper | Probabilistic Safety Assessment and Risk Management / Fuel Cycle | doi.org/10.13182/NT89-A34218
