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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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
Dragonfly, a Pu-fueled drone heading to Titan, gets key NASA approval
Curiosity landed on Mars sporting a radioisotope thermoelectric generator (RTG) in 2012, and a second NASA rover, Perseverance, landed in 2021. Both are still rolling across the red planet in the name of science. Another exploratory craft with a similar plutonium-238–fueled RTG but a very different mission—to fly between multiple test sites on Titan, Saturn’s largest moon—recently got one step closer to deployment.
On April 25, NASA and the Johns Hopkins University Applied Physics Laboratory (APL) announced that the Dragonfly mission to Saturn’s icy moon passed its critical design review. “Passing this mission milestone means that Dragonfly’s mission design, fabrication, integration, and test plans are all approved, and the mission can now turn its attention to the construction of the spacecraft itself,” according to NASA.
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Design of a Simulated Void-Reactivity Feedback in a Boiling Water Reactor Loop
H. V. Kok, T. H. J. J. Van der Hagen
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 1-11
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A3009
RAPID-A Fast Reactor Concept Without Any Control Rods
Mitsuru Kambe
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 12-24
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A3010
Radiological Impact at the Extraction Stage of the Thorium Fuel Cycle
J. P. Schapira, R. K. Singhal
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 25-34
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A3011
Fuel Element Burnup Determination in Mixed TRIGA Core Using Reactor Calculations
Matjaz Ravnik, Tomaz Zagar, Andreja Persic
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 35-45
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A3012
Finite Element-Based Vibration Analysis of WWER-440 Reactors
Eberhard Alstadt, Frank-Peter Weiss
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 46-57
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A3013
Turbulence Simulation in Tube Bundle Geometries Using the Dynamic Subgrid-Scale Model
Yassin A. Hassan, Hagop R. Barsamian
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 58-74
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A3014
Natural Circulation Experiments at the ISB-VVER Integral Test Facility and Calculations Using the Thermal-Hydraulic Code ATHLET
Eckhard Krepper, Horst-Michael Prasser
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 75-86
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A3015
RELAP5-3D Multidimensional Heat Conduction Enclosure Model for RBMK Reactor Application
Seungho Paik
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 87-102
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A3016
Precipitation of Uranium and Plutonium from Alkaline Salt Solutions
David T. Hobbs
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 103-112
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT128-103
Development and Validation of ALFUS: An Irradiation Behavior Analysis Code for Metallic Fast Reactor Fuels
Takanari Ogata, Takeshi Yokoo
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 113-123
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT99-A3018
Multinodal Treatment of Production, Decay, and Spreading of Radioactive Isotopes
Péter Vértes
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 124-130
Technical Note | Reactor Safety | doi.org/10.13182/NT99-A3019
Overview of RETRAN Related Activities
Lance J. Agee
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 131-138
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3020
Implementation of an Improved Interfacial Mass and Energy Transfer Model in RETRAN-3D
Rafael Macian, Peter Cebull, Paul Coddington, Mark Paulsen
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 139-152
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3021
Evaluation of the Slip Options in RETRAN-3D
Daniel Maier, Paul Coddington
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 153-168
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3022
Tenth Cofrentes Reload Licensing Analysis with RETRAN-03 Methodology
Rafael de la Fuente, J. Manuel Dey, Pablo G. Sedano, Pedro Mata
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 169-185
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3023
Analyses of Startup Test, Reload Limiting Transient, and Plant Event for the Kuosheng BWR-6 Related to MSIV Closure
Jan-Ru Tang, Shao-Shei Ma, Jan-Der Wang, Show-Chyuan Chiang, Lin-Yao Chou, Ching-Chuan Yao, Ying-Tsen Liao
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 186-204
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3024
Modeling and Simulation of the First ABWR for Validation of RETRAN-3D
Michitsugu Mori
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 205-215
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3025
Mihama Unit 2 Steam Generator Tube Rupture Analysis
Tomohiko Tamaki, Masanori Ohtani, Yasuharu Kawabe
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 216-224
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3026
VIPRE-02 Subchannel Validation Against NUPEC BWR Void Fraction Data
Yacine Aounallah, Paul Coddington
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 225-232
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3027
Main-Steam-Line-Break Analysis of TMI-1 Using RETRAN-3D
Craig E. Peterson, John G. Shatford, Ardesar Irani, Nicholas G. Trikouros, Antonio F. Dias, Lance J. Agee
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 233-244
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3028
Plutonium Recycling in a Full-MOX 900-MW(electric) PWR: Physical Analysis of Accident Behaviors
Sylvie Aniel-Buchheit, André Puill, Richard Sanchez, Mireille Coste
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 245-256
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A3029
A Study on Regional Stability Analysis Methodology with a One-Point Neutron Kinetics Model
Yutaka Takeuchi, Yukio Takigawa, Shiho Miyamoto
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 257-275
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A3030
Application of Neural Networks to Analyze Load-Follow Operation in a Pressurized Water Reactor
Seung Hwan Seong, Un Chul Lee, Si Hwan Kim, Jin Wook Jang
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 276-283
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT99-A3031
Comparisons of Calculated and Measured 237Np, 241Am, and 243Am Concentrations as a Function of the 240Pu/239Pu Isotopic Ratio in Spent Fuel
William S. Charlton, William D. Stanbro, R. T. Perry, Bryan L. Fearey
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 285-299
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A3032
Liquid-Metal-Bonded Gap for Light Water Reactor Fuel Rods
Yeon Soo Kim, D. R. Olander, S. K. Yagnik
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 300-312
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A3033
Applicability of the CONTAIN Code Heat and Mass-Transfer Models to Asymmetrically Heated Vertical Channels
Rajgopal Vijaykumar, Mohsen Khatib-Rahbar
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 313-326
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A3034
Application of a Genetic Neuro-Fuzzy Logic to Departure from Nucleate Boiling Protection Limit Estimation
Man Gyun Na
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 327-340
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT99-A3035
Impurity Evaluation of Fused Lithium Chloride Salt for a Pilot-Scale Spent-Oxide-Fuel Reduction Process
C. S. Eberle
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 341-358
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A3036
Radiolytic and Chemical Degradation of Strong Acidic Ion-Exchange Resins: Study of the Ligands Formed
L. R. van Loon, W. Hummel
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 359-371
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A3037
The Effect of Degradation Products of Strong Acidic Cation Exchange Resins on Radionuclide Speciation: A Case Study with Ni2+
W. Hummel, L. R. van Loon
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 372-387
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A3038
The Degradation of Strong Basic Anion Exchange Resins and Mixed-Bed Ion-Exchange Resins: Effect of Degradation Products on Radionuclide Speciation
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 388-401
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A3039
The Effective Delayed Neutron Fraction for Bare-Metal Criticals
Sol Pearlstein
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 402-408
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A3040
