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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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April 3–5, 2025
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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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System Modeling and Reactor Design Studies of the Advanced Thermionic Initiative Space Nuclear Reactor
Hsing H. Lee, Shahab Abdul-Hamid, Andrew C. Klein
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 1-21
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35271
Anticipated Transient Without Scram Analysis of the Simplified Boiling Water Reactor Following Main Steam Isolation Valve Closure with Boron Injection
Hasna J. Khan, Hsiang-Shou Cheng, Upendra S. Rohatgi
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 22-34
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35272
Analytical Study of Subcritical Vapor Explosions Using Thermal Detonation Wave Theory
Bassam I. Shamoun, Michael L. Corradini
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 35-45
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35273
Liquid-Metal/Water Interactions in a Shock Tube
Gordana Vukovic, Michael L. Corradini
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 46-60
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35274
Average Irradiation Temperature for the Analysis of In-Pile Integral Measurements
Abdellatif M. Yacout, Won-Sik Yang, Gerard L. Hofman, Yuri Orechwa
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 61-72
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35275
Thermodynamic Properties of Water in Compacted Sodium Montmorillonite
Yuji Torikai, Seichi Sato, Hiroshi Ohashi
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 73-80
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35276
Thermodynamic Study in Support of Pressurized Water Reactor Specific Reactor Water Chemistry
Kostadin A. Dinov, Kazuo Kasahara
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 81-90
Technical Paper | Material | doi.org/10.13182/NT96-A35277
The Influence of Complex Pore Shapes on Thermal Conductivity
Klaas Bakker, Rudy J. M. Konings
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 91-99
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35278
Development and Application of Neutron Field Optimization Parameters for an Accelerator-Based Neutron Source for Boron Neutron Capture Therapy
Jeffrey E. Woollard, Thomas E. Blue, Nilendu Gupta, Reinhard A. Gahbauer
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 100-113
Technical Paper | Radiation Protection | doi.org/10.13182/NT96-A35279
Development of Pyrometallurgical Partitioning of Actinides from High-Level Radioactive Waste Using a Reductive Extraction Step
Takatoshi Hijikata, Masahiro Sakata, Hajime Miyashiro, Kensuke Kinoshita, Tatsuhiro Higashi, Tadaharu Tamai
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 114-121
Technical Note | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35280
The Specific Research and Development Contribution of Commissariat à I’Energie Atomique for the Disposal of Radioactive Waste Containing Long-Lived Elements
Jean-Claude Petit
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 125-134
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35257
Legislative and Regulatory Aspects of Radioactive Waste Management in France
Jean-Christophe Niel
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 135-137
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35258
The Role of Characterization as an Interface Between Safety Authorities, Waste Producers, Radwaste Managers, and Research Laboratories
Denis Alexandre
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 138-145
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35259
Characterization of Low- and Medium-Activity Radioactive Waste
Alain P. M. Heres, Maxy C. Noe
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 146-152
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35260
Neutron Moisture Meter Measurement in Waste Packages
Josée Perfettini
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 153-161
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35261
Nondestructive Determination of Activity
Bernard Chabalier
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 162-172
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35262
Destructive Procedures and Analytical Tools for the Study of Radwaste Packages
Dominique Grec
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 173-177
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35263
Determination of Physical Homogeneity by Gamma-Ray Imaging
Jean-Luc Pettier
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 178-191
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35264
Studies on Important Radionuclides for the Safety of a Radioactive Waste Disposal Site: Correlation Between Easily Measurable Gamma Emitters and Long-Lived Radionuclides
Alain Raymond, Brigitte Lagarde, Annick Pitiot
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 192-197
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35265
Review of the Development of Waste Form Conditioning Processes in France
C. Courtois, J. P. Moncouyoux, E. Revertegat
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 198-207
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35266
Studies on the Degassing of Waste Packages
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 208-213
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35267
Overview of the French Program on Leaching Various Waste Forms
J. C. Nomine, J. F. Ferriot
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 214-227
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35268
Waste Forms—French Leaching Test Compared with Lysimeter Tests
J. F. Ferriot, J. C. Nomine, V. Reynaud
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 228-242
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35269
Advanced Neutron Source Enrichment Study
Robert A. Bari, Hans Ludewig, John R. Weeks
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 243-265
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A15836
Method and Results of Safety Evaluation of the High-Temperature Engineering Test Reactor
Shigeaki Nakagawa, Kazuhiko Kunitomi, Kazuhiro Sawa
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 266-280
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A15837
Thermal Bonding of Light Water Reactor Fuel Using Nonalkaline Liquid-Metal Alloy
Richard F. Wright, James S. Tulenko, Glen J. Schoessow, Richard G. Connell, Jr., Mark A. Dubecky, Thad Adams
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 281-292
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A15838
Ion-Exchange Selectivity of Tertiary Pyridine-Type Anion-Exchange Resin for Treatment of Spent Nuclear Fuels
Masanobu Nogami, Masao Aida, Yasuhiko Fujii, Akira Maekawa, Shinobu Ohe, Hiroomi Kawai, Morihiro Yoneda
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 293-297
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A15839
Considerations of Autocatalytic Criticality of Fissile Materials in Geologic Respositories
William E. Kastenberg, Per F. Peterson, Joonhong Ahn, J. Burch, G. Casher, Paul L. Chambré, Ehud Greenspan, Donald R. Olander, Jasmina L. Vujic, B. Bessinger, Neville G. W. Cook, Fiona M. Doyle, L. Brun Hilbert, Jr.
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 298-310
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-2
Design of a Small-Animal Thermal Neutron Irradiation Facility at the Brookhaven Medical Research Reactor
Hungyuan B. Liu
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 311-319
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT96-A15841
Loss-of-Normal-Feedwater Sensitivity Studies for AP600 Behavior Characterization*
Gianfranco Saiu, Gabriele del Nero, Antonio Madonna, Giuseppe Marella, Andrea Orazi
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 320-332
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A15842
Development and Application of a Fully Implicit Fluid Dynamics Code for Multiphase Flow
Tadashi Morii, Yumi Ogawa
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 333-341
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A15843
A Hybrid Approach for Detecting and Isolating Faults in Nuclear Power Plant Interacting Systems
J. Wesley Hines,* Don W. Miller, Brian K. Hajek
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 342-358
Technical Paper | Reactot Operation | doi.org/10.13182/NT96-A15844
Modeling of Boron Species in the Falcon 17 and ISP-34 Integral Tests
Mihalis Lazaridis, Joaquim Areia Capitão, Yannis Drossinos
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 359-367
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT96-A15845
