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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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February 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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Simplified Boiling Water Reactor Thermal-Hydraulic Performance: A RELAP5/MOD2 Model Simulation
P. Barbucci, L. Bella
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 1-8
Technical Paper | Fission Reactor | doi.org/10.13182/NT95-A15847
Radial Resonance Captures in 238U Metal Rods and Spatial Resonance Production of 239Pu in Uranium-Oxide Fuels
Donald Bogart
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 9-20
Technical Paper | Fission Reactor | doi.org/10.13182/NT95-A15848
Aging Effects on Time-Dependent Nuclear Plant Component Unavailability: An Investigation of Variations from Static Calculations
Rob D. Radulovich, William E. Vesely, Tunc Aldemir
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 21-41
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A15849
Evaluation of Reflooding Effects on an Overheated Boiling Water Reactor Core in a Small Steam-Line Break Accident Using MAAP, MELCOR, and SCDAP/RELAP5 Computer Codes
I. Lindholm, E. Pekkarinen, H. Sjövall
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 42-57
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A15850
Qualification of a Passive Catalytic Module for Hydrogen Mitigation
Karsten Fischer
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 58-62
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A15851
A Route-Specific System for Risk Assessment of Radioactive Materials Transportation Accidents
John E. Moore, Gary M. Sandquist, David M. Slaughter
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 63-78
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT95-A15852
Thermal and Thermomechanical Analyses for Disposal in Drifts of a Repository in Rock Salt
Alexandra Pudewills, Nina Müller-Hoeppe, Reiner Papp
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 79-88
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT95-A15853
Fast Multiple-Path Model to Calculate Radionuclide Release from the Near Field of a Repository
L. Romero, L. Moreno, I. Neretnieks
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 89-98
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT95-A15854
The Fast Multiple-Path NUCTRAN Model—Calculating the Radionuclide Release from a Repository
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 99-107
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT95-A15855
Framatome Antistratification Device for Steam Generator Feedwater Nozzle: Effectiveness, Qualification Test, and On-Site Measurements
Christophe Poussin, Alain Holcblat
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 108-121
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A15856
Experimental Study on Performance of a Hybrid Baffle Plate for the Water-Wall-Type Passive Containment Cooling System
Tadashi Fujii, Yoshiyuki Kataoka, Michio Murase, Kenji Tominaga
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 122-131
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A15857
Calculated Shielding Characteristics of Eight Materials for Neutrons and Secondary Photons Produced by Monoenergetic Source Neutrons with Energies Less Than 400 MeV
Noriyoshi Nakanishi, Takashi Shikata, Shin Fujita, Toshiso Kosako
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 132-141
Technical Paper | Radiation Protection | doi.org/10.13182/NT95-A15858
Improved Neutronics Model of the High Flux Isotope Reactor
S. Goluoglu, H. L. Dodds
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 142-153
Technical Note | Fission Reactor | doi.org/10.13182/NT95-A15859
Mitigation of an Anticipated Transient Without Scram Event in A Simplified Boiling Water Reactor by the Insertion of Fine-Motion Control Rods
Hasna J. Khan, Hsiang S. Cheng, Upendra S. Rohatgi
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 155-168
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35170
Independent Assessment of Melcor as A Severe Accident Thermal-Hydraulic/Source Term Analysis Tool
I. K. Madni
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 169-180
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35171
A Comparative Simulation of Feed and Bleed Operation During the Total Loss of Feedwater Event by RELAP5/MOD3 and CEFLASH-4AS/REM Computer Codes
Young Min Kwon, Tae Sun Ro, Jin Ho Song
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 181-193
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35172
Irradiation Performance of Fast Flux Test Facility Drivers Using D9 Alloy
A. L. Pitner, B. C. Gneiting, F. E. Bard
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 194-203
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35173
Choice of A Process Design for Simultaneous Detritiation and Upgrading of Heavy water for the Advanced Neutron Source
A. I. Miller, D. A. Spagnolo, J. R. DeVore
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 204-213
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT95-A35174
Taiwan Power Company’s Power Distribution Analysis and Fuel Thermal Margin Verification Methods for Pressurized Water Reactors
Ping-Hue Huang
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 214-226
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35175
Heat Transfer from A Plate Cooled by A Water Film with Countercurrent Air Flow
W. Ambrosini, A. Manfredini, F. Mariotti, F. Oriolo, P. Vigni
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 227-237
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35176
Thermal-Hydraulic Modeling and Severe Accident Radionuclide Transport
F. Oriolo, W. Ambrosini, G. Fruttuoso, F. Parozzi, R. Fontana
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 238-249
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35177
Probabilistic Analysis of Limiting Conditions for Operation Action Requirements Including Risk of Shutdown
T. Mankamo, I. S. Kim, P. K. Samanta
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 250-265
Technical Paper | Reactor Operation | doi.org/10.13182/NT95-A35178
Development of the On-Line Operator Aid System OASYS Using A Rule-Based Expert System and Fuzzy Logic for Nuclear Power Plants
Soon Heung Chang, Ki Sig Kang, Seong Soo Choi, Han Gon Kim, Hee Kyo Jeong, Chul Un Yi
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 266-294
Technical Paper | Reactor Control | doi.org/10.13182/NT95-A35179
Transient Gap Conductance in Nuclear Fuel Rods
G. Dharmadurai
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 295-298
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35180
Validation of the Assert Subchannel Code: Prediction of Critical Heat Flux in Standard and Nonstandard Candu Bundle Geometries
M. B. Carver, J. C. Kiteley, R. Q.-N. Zhou, S. V. Junop, D. S. Rowe
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 299-314
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35156
Prediction of Dryout Performance for Boiling Water Reactor Fuel Assemblies Based on Subchannel Analysis with the Rings Code
P. Knabe, F. Wehle
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 315-323
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35157
A Perspective on Large eddy Simulation of Problems in the Nuclear Industry
Yassin A. Hassan, John M. Pruitt, David A. Steininger
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 324-330
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35158
The THYC Three-Dimensional Thermal-Hydraulic Code for Rod Bundles: Recent Developments and Validation Tests
Sylvie Aubry, Christian Caremoli, Jean Olive, Paul Rascle
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 331-345
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35159
The Application of Computational Fluid Dynamics to Critical Heat Flux
James H. Stuhmiller, Paul J. Masiello, Govinda S. Srikantiah, Lance J. Agee
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 346-354
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35160
A Utility Perspective on Subchannel Analysis
Gregg B. Swindlehurst
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 355-358
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35161
Equilibrium Quality and Mass Flux Distributions in an Adiabatic Three-Subchannel Test Section
George Yadigaroglu, Athan Maganas
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 359-372
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35162
Reactor Subchannel Analysis—Electric Power Research Institute Perspective
G. Srikantiah
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 373-381
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35163
The Japanese Utilities’ Expectations for Subchannel Analysis
Akio Toba, Akira Omoto
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 382-387
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35164
Void Fraction Distribution in A Boiling Water Reactor Fuel Assembly and the Evaluation of Subchannel Analysis Codes
Akira Inoue, Masanobu Futakuchi, Makoto Yagi, Toru Mitsutake, Shin-Ichi Morooka
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 388-400
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35165
Subchannel Thermal-Hydraulic Analysis at AP600 Low-Flow Steam-Line-Break Conditions
T. Morita, C. A. Olson, Y. X. Sung, J. F. Connelley, Jr., E. H. Novendstern, S. Kapil, P. W. Rosenthal
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 401-411
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35166
Pressurized Water Reactor Fuel Assembly Subchannel Void Fraction Measurement
Yoshiei Akiyama, Keiichi Hori, Keiji Miyazaki, Kaichiro Mishima, Shigekazu Sugiyama
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 412-421
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35167
