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Division Spotlight
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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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 Technology
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Latest News
Deep Isolation validates its disposal canister for TRISO spent fuel
Nuclear waste disposal technology company Deep Isolation announced it has successfully completed Project PUCK, a government-funded initiative to demonstrate the feasibility and potential commercial readiness of its Universal Canister System (UCS) to manage TRISO spent nuclear fuel.
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Influence of the Pipe Diameter on the Structure of the Gas-Liquid Interface in a Vertical Two-Phase Pipe Flow
H.-M. Prasser, M. Beyer, A. Böttger, H. Carl, D. Lucas, A. Schaffrath, P. Schütz, F.-P. Weiss, J. Zschau
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 3-22
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3657
Two-Phase Void Drift Phenomena in a 2 × 3 Rod Bundle: Flow Redistribution Data and Their Analysis
Michio Sadatomi, Akimaro Kawahara, Tsukasa Kuno, Keiko Kano
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 23-37
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT152-23
Suitability of Drift-Flux Models, Void-Fraction Evolution, and 3-D Flow Pattern Visualization During Stationary and Transient Flashing Flow in a Vertical Pipe
Annalisa Manera, Horst-Michael Prasser, Tim H. J. J. van der Hagen
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 38-53
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-3
Theoretical Foundation for an Electromagnetic Two-Phase Flowmetry
Yeh-Chan Ahn, Byung Do Oh, Moo Hwan Kim
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 54-70
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3660
Investigation of the Noncondensable Effect and the Operational Modes of the Passive Condenser System
Seungmin Oh, Shripad T. Revankar
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 71-86
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3661
Lookup Tables for Predicting CHF and Film-Boiling Heat Transfer: Past, Present, and Future
D. C. Groeneveld, L. K. H. Leung, Y. Guo, A. Vasic, M. El Nakla, S. W. Peng, J. Yang, S. C. Cheng
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 87-104
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT152-87
Application of the Post-Boiling-Transition Standard to Licensing Analysis
Shinya Mizokami, Hideya Kitamura, Yoshiro Kudo, Seiichi Komura, Yoshifumi Nagata, Shinichi Morooka
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 105-117
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3663
Life Estimation of PWR Steam Generator U-Tubes Subjected to Foreign Object-Induced Fretting Wear
Jong Chull Jo, Myung Jo Jhung, Woong Sik Kim, Hho Jung Kim
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 118-128
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3664
A Three-Dimensional Two-Fluid Modeling of Stratified Flow with Condensation for Pressurized Thermal Shock Investigations
W. Yao, D. Bestion, P. Coste, M. Boucker
Nuclear Technology | Volume 152 | Number 1 | October 2005 | Pages 129-142
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3665
Limiting Factors for External Reactor Vessel Cooling
F. B. Cheung
Nuclear Technology | Volume 152 | Number 2 | November 2005 | Pages 145-161
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3666
Critical Heat Flux Experiments on the Reactor Vessel Wall Using 2-D Slice Test Section
Yong Hoon Jeong, Soon Heung Chang, Won-Pil Baek
Nuclear Technology | Volume 152 | Number 2 | November 2005 | Pages 162-169
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3667
Development of an Enhanced Core Catcher for Improving In-Vessel Retention Margins
J. L. Rempe, K. G. Condie, D. L. Knudson, K. Y. Suh, F. B. Cheung, S. B. Kim
Nuclear Technology | Volume 152 | Number 2 | November 2005 | Pages 170-182
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3668
KAERI Integral Effect Test Program and the ATLAS Design
Won-Pil Baek, Chul-Hwa Song, Byong-Jo Yun, Tae-Soon Kwon, Sang-Ki Moon, Sung-Jae Lee
Nuclear Technology | Volume 152 | Number 2 | November 2005 | Pages 183-195
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3669
Evolution of Design Methodologies for Next Generation of Reactor Pressure Vessels and Extensive Role of Thermal-Hydraulic Numerical Tools
Serge Bellet, Nicolas Goreaud, Norbert Nicaise
Nuclear Technology | Volume 152 | Number 2 | November 2005 | Pages 196-209
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3670
Experimental Study on Flow Optimization in Upper Plenum of Reactor Vessel for a Compact Sodium-Cooled Fast Reactor
Nobuyuki Kimura, Kenji Hayashi, Hideki Kamide, Masami Itoh, Tadashi Sekine
Nuclear Technology | Volume 152 | Number 2 | November 2005 | Pages 210-222
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3671
Computational Study of Thermal Striping in an Upper Plenum of Kalimer
Seok-Ki Choi, Myung-Hwan Wi, Won-Dae Jeon, Seong-O Kim
Nuclear Technology | Volume 152 | Number 2 | November 2005 | Pages 223-238
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3672
New Challenges in Computational Thermal Hydraulics
George Yadigaroglu, Djamel Lakehal
Nuclear Technology | Volume 152 | Number 2 | November 2005 | Pages 239-251
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3673
Analysis of Severe Accident Management Strategy for a BWR-4 Nuclear Power Plant
Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 253-265
Technical Paper | Fission Reactors | doi.org/10.13182/NT05-A3674
A Feasibility Study of a Steam Methane Reforming Hydrogen Production Plant with a Sodium-Cooled Fast Reactor
Yoshitaka Chikazawa, Mamoru Konomura, Shouji Uchida, Hiroyuki Sato
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 266-272
Technical Paper | Fission Reactors | doi.org/10.13182/NT05-A3675
Ballooning Experiments with VVER Cladding
Zoltán Hózer, Csaba Gyuori, Márta Horváth, Imre Nagy, László Maróti, Lajos Matus, Péter Windberg, József Frecska
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 273-285
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT05-A3676
Development and Experimental Verification of the Numerical Simulation Method for the Quasi-Steady SWR Phenomena in an LMR Steam Generator
Jae-Hyuk Eoh, Ji-Young Jeong, Seong-O Kim, Dohee Hahn, Nam-Cook Park
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 286-301
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3677
MELCOR Analysis of Steam Generator Tube Creep Rupture in Station Blackout Severe Accident
Y. Liao, K. Vierow
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 302-313
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-5
Safety Investigation of Liquid-Metal-Cooled Nuclear Systems with Heat Exchanger in the Risers of Simple Flow-Path Pool Design
Johan Carlsson, Hartmut U. Wider
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 314-323
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3679
Computational Analysis of the Thermal-Hydraulic Characteristics of the Encapsulated Nuclear Heat Source
Yoshihisa Nishi, Nobuyuki Ueda, Izumi Kinoshita, Ehud Greenspan
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 324-338
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3680
Radioisotope Deposition on Interior Building Surfaces: Air Flow and Surface Roughness Influences
Bobby E. Leonard
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 339-353
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT05-A3681
Monte Carlo-Based Analysis for the Transmutation of Transuranic Waste Recycled in Light Water Reactors
Kenneth S. Allen, Edward P. Naessens, Jr.
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 354-366
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT05-A3682
Neutronics of Minor-Actinide Burning Accelerator-Driven Systems with Ceramic Fuel
J. Wallenius, M. Eriksson
Nuclear Technology | Volume 152 | Number 3 | December 2005 | Pages 367-381
Technical Paper | Accelerators | doi.org/10.13182/NT152-367
