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Operations & Power
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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Development of Phenomena Identification and Ranking Tables for the Advanced CANDU Reactor
N. K. Popov, H. Sills, A. Abdul-Razzak
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 2-17
Technical Paper | Best Estimate Methods | doi.org/10.13182/NT07-A3820
Evaluation of Weak Heat Conduction Mechanism Model for Long-Term LOCAs in RBMK-1500
E. Uspuras, A. Kaliatka
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 18-25
Technical Paper | Best Estimate Methods | doi.org/10.13182/NT07-A3821
Accurate Solution of the Nonlinear Partial Differential Equations from Thermal Hydraulics
Vincent A. Mousseau
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 26-35
Technical Paper | Best Estimate Methods | doi.org/10.13182/NT07-A3822
Detailed MCNP Modeling of BR2 Fuel with Azimuthal Variation
Silva Kalcheva, Edgar Koonen, Pol Gubel
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 36-55
Technical Paper | Best Estimate Methods | doi.org/10.13182/NT07-A3823
Scaling of the Small-Scale Thermal-Hydraulic Transient to the Real Nuclear Power Plant
Stojan Petelin, Borut Mavko, Bostjan Koncar, Yassin A. Hassan
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 56-68
Technical Paper | Best Estimate Methods | doi.org/10.13182/NT07-A3824
The State-of-the-Art Theory and Applications of Best-Estimate Plus Uncertainty Methods
Andrej Prosek, Borut Mavko
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 69-79
Technical Note | Best Estimate Methods | doi.org/10.13182/NT07-1
On the Choice Between Segregated and Coupled Solver Approaches When Using Computational Fluid Dynamics for Gas-Cooled Reactor Analysis
David G. Schowalter, Nilanjana Basu, Ajey Walavalkar, Richard R. Schultz
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 80-82
Technical Note | Best Estimate Methods | doi.org/10.13182/NT07-A3826
Major Challenges to Modeling Aerosol Retention Near a Tube Breach During Steam Generator Tube Rupture Sequences
Luis E. Herranz, C. L. del Prá, A. Dehbi
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 83-93
Technical Paper | Reactor Safety | doi.org/10.13182/NT07-A3827
Fuel Cycle Analysis of a Subcritical Fast Helium-Cooled Transmutation Reactor with a Fusion Neutron Source
J. W. Maddox, W. M. Stacey
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 94-108
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT07-A3828
An Investigation of an In-Vessel Corium Retention Strategy for the Wolsong Pressurized Heavy Water Reactor Plants
Soo-Yong Park, Young-Ho Jin, Yong-Mann Song
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 109-115
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT07-A3829
Performance of Planar High-Temperature Electrolysis Stacks for Hydrogen Production from Nuclear Energy
James E. O'Brien, Carl M. Stoots, J. Stephen Herring, Joseph J. Hartvigsen
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 118-131
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3830
Computational Fluid Dynamics Model of a Planar Solid-Oxide Electrolysis Cell for Hydrogen Production from Nuclear Energy
Grant L. Hawkes, James E. O'Brien, Carl M. Stoots, J. Stephen Herring, Mehrdad Shahnam
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 132-144
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3831
Optimization of Advanced High-Temperature Brayton Cycles with Multiple-Reheat Stages
Haihua Zhao, Per F. Peterson
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 145-157
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3832
Hot-Channel Stability of Supercritical Water-Cooled Reactors - I: Steady-State and Sliding Pressure Startup
Jiyun Zhao, Pradip Saha, Mujid S. Kazimi
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 158-173
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3833
Hot-Channel Stability of Supercritical Water-Cooled Reactors - II: Effect of Water Rod Heating and Comparison with BWR Stability
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 174-190
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3834
Development of BWR Regional Stability Experimental Facility SIRIUS-F, Which Simulates Thermal Hydraulics-Neutronics Coupling, and Stability Evaluation of ABWRs
Masahiro Furuya, Takanori Fukahori, Shinya Mizokami
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 191-207
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3835
Investigation of a Passive Condenser System of an Advanced Boiling Water Reactor
Seungmin Oh, Haijing Gao, Shripad T. Revankar
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 208-218
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3836
Critical Heat Flux in Square- and Nonsquare-Array Rod Bundles for Advanced Light Water Reactors
Dae-Hyun Hwang, Kyong-Won Seo, Chung-Chan Lee
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 219-228
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3837
Computational Fluid Dynamics Analysis of Heat Transfer to Heavy Liquid Metals in Bare Rod Bundles
X. Cheng, N. I. Tak
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 229-236
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT158-229
Improved Turbulence Modeling for Performance Evaluation of Novel Fuel Designs
Emilio Baglietto, Hisashi Ninokata
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 237-248
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3839
Computational Model for Turbulent Flow Around a Grid Spacer with Mixing Vane
Tsutomu Ikeno, Takeo Kajishima
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 249-260
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3840
On the Modeling of Gas Bubble Evolution and Transport Using Coupled Level-Set/CFD Method
Bartlomiej Z. Wierzbicki, Steven P. Antal, Michael Z. Podowski
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 261-274
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3841
Experimental Investigation on Bubble Turbulent Diffusion in a Vertical Large-Diameter Pipe by Wire-Mesh Sensors and Correlation Techniques
Annalisa Manera, Horst-Michael Prasser, Dirk Lucas
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 275-290
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3842
Modeling the Evolution of Bubbly Flow Along a Large Vertical Pipe
Dirk Lucas, Eckhard Krepper, H.-M. Prasser
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 291-303
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3843
Measurement of the Deposition Rate of Droplets in a Vertical Tube Containing a Flow Obstacle
Tomio Okawa, Akio Kotani, Naoya Shimada, Isao Kataoka
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 304-313
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3844
Design and Economic Evaluation of an Advanced Tight-Lattice Core for the IRIS Integral Primary System Reactor
J. G. B. Saccheri, N. E. Todreas, M. J. Driscoll
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 315-347
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3845
Three-Region Core Design for 200-MW(electric) Molten-Salt Reactor with Thorium-Uranium Fuel
Koshi Mitachi, Takahisa Yamamoto, Ritsuo Yoshioka
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 348-357
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3846
Simulation of the Flow Rotation and Mixing in the Downcomer of a VVER-1000 Reactor
Emilian Popov, Boyan Ivanov, Kostadin N. Ivanov, Stilyana Mladenova
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 358-365
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3847
A Study of the Liquid Entrainment and Vapor Pull-Through in an Angled Branch Line
Yong Jin Cho, Gyoo Dong Jeun
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 366-377
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3848
Results of the Triggered Steam Explosions from the TROI Experiment
J. H. Kim, I. K. Park, B. T. Min, S. W. Hong, S. H. Hong, J. H. Song, H. D. Kim
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 378-395
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3849
Assessment of APR1400 ECCS Capability Against Large-Break LOCA Scenario by RELAP5/MOD3 Code
Sang Won Lee, Han Gon Kim, Seung Jong Oh
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 396-407
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3850
Effects of Accelerator-Driven Transmutation System on Radiotoxicity of High-Level Radioactive Wastes
Joonhong Ahn, Myeongguk Cheon, Ehud Greenspan
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 408-430
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT07-A3851
