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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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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Evolution of Sodium Technology R&D Actions Supporting French Liquid-Metal Fast Breeder Reactors
G. Rodriguez, F. Baque, J. C. Astegiano
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 3-15
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3601
Distinguished Achievements of a Quarter-Century Operation and a Promising Project Named MK-III in JOYO
Yukimoto Maeda, Takafumi Aoyama, Toshihiro Odo, Satoru Nakai, Soju Suzuki
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 16-36
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3602
Lifetime Extension of the Phénix Plant
J. Guidez, P. Le Coz, L. Martin, P. Mariteau, R. Dupraz
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 37-43
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3603
The Dounreay PFR Liquid-Metal Disposal Project
D. V. Sherwood, A. Comline, J. Small, J. Blyth
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 44-55
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3604
Upgrade of Cooling System Heat Removal Capacity of the Experimental Fast Reactor JOYO
Kazunori Isozaki, Takashi Ashida, Kouzou Sumino, Satoru Nakai
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 56-66
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3605
Review of In-Service Inspection and Repair Technique Developments for French Liquid Metal Fast Reactors
F. Baque
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 67-78
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3606
Cleaning Cesium Radionuclides from BN-350 Primary Sodium
O. G. Romanenko, K. J. Allen, D. M. Wachs, H. P. Planchon, P. B. Wells, J. A. Michelbacher, P. Nazarenko, I. Dumchev, V. Maev, B. Zemtzev, L. Tikhomirov, V. Yakovlev, A. Synkov
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 79-99
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3607
Recent Sodium Technology Development for the Decommissioning of the Rapsodie and Superphénix Reactors and the Management of Sodium Wastes
G. Rodriguez, O. Gastaldi, F. Baque
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 100-110
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3608
A Reliable Steam Generator That Will Allow the Elimination of the Secondary Sodium Circuit in an LMFBR
D. V. Sherwood, Y. Chikazawa
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 111-119
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3609
Nuclear Fuel Leasing, Recycling, and Proliferation: Modeling a Global View
Victor H. Reis, Matthew P. Crozat, Jor-Shan Choi, Robert Hill
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 121-131
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT05-A3610
Analysis of Fluid Flow and Solute Transport in a Fracture Intersecting a Canister with Variable Aperture Fractures and Arbitrary Intersection Angles
Longcheng Liu, Ivars Neretnieks
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 132-144
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3611
Comparison of Severe Accident Results Among SCDAP/RELAP5, MAAP, and MELCOR Codes
Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 145-152
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3612
Pyroprocessing of Light Water Reactor Spent Fuels Based on an Electrochemical Reduction Technology
Hirokazu Ohta, Tadashi Inoue, Yoshiharu Sakamura, Kensuke Kinoshita
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 153-161
Technical Paper | Reprocessing | doi.org/10.13182/NT05-A3613
A Subcritical, Gas-Cooled Fast Transmutation Reactor with a Fusion Neutron Source
W. M. Stacey, V. L. Beavers, W. A. Casino, J. R. Cheatham, Z. W. Friis, R. D. Green, W. R. Hamilton, K. W. Haufler, J. D. Hutchinson, W. J. Lackey, R. A. Lorio, J. W. Maddox, J. Mandrekas, A. A. Manzoor, C. A. Noelke, C. de Oliveira, M. Park, D. W. Tedder, M. R. Terry, E. A. Hoffman
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 162-188
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT05-A3614
Incidence of High Nitrogen in Sintered Uranium Dioxide: A Case Study
Palanki Balakrishna, B. Narasimha Murty, M. Anuradha, R. B. Yadav, R. N. Jayaraj
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 189-195
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT05-A3615
Detection and Localization of Money Bills Concealed Behind Wooden Walls Using Compton Scattering
Jason A. Van Wart, Esam M. A. Hussein, Edward J. Waller
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 196-202
Technical Paper | Radioisotopes | doi.org/10.13182/NT05-A3616
Development of a Fissile Materials Irradiation Capability for Advanced Fuel Testing at the MIT Research Reactor
Lin-Wen Hu, John A. Bernard, Pavel Hejzlar, Gordon Kohse
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 203-208
Technical Note | Materials for Nuclear Systems | doi.org/10.13182/NT05-A3617
The Economics of Reprocessing Versus Direct Disposal of Spent Nuclear Fuel
Matthew Bunn, John P. Holdren, Steve Fetter, Bob Van Der Zwaan
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 209-230
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT05-A3618
Assessment of the RANS Turbulence Models for a Turbulent Flow and Heat Transfer in a Rod Bundle
Wang-Kee In, Tae-Hyun Chun
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 231-250
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3619
Investigation of Containment Flooding Strategy for Mark-III Nuclear Power Plant with MAAP4
Wei-Nian Su, Shih-Jen Wang, Show-Chyuan Chiang
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 251-262
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3620
Hydrogen Mitigation Strategy of the APR1400 Nuclear Power Plant for a Hypothetical Station Blackout Accident
Jongtae Kim, Seong-Wan Hong, Sang-Baik Kim, Hee-Dong Kim
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 263-282
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3621
Improvements in Predicting Void Fraction in Subcooled Boiling
Kwi Seok Ha, Yong Bum Lee, Hee Cheon No
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 283-292
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3622
Design of a Software Sensor for Feedwater Flow Measurement Using a Fuzzy Inference System
Man Gyun Na, Sun Ho Shin, Dong Won Jung
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 293-302
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT05-A3623
On the Radiolytic Decomposition of Colloidal Silver Iodide in Aqueous Suspension
Salih Güntay, Robin C. Cripps, Bernd Jäckel, Horst Bruchertseifer
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 303-314
Technical Paper | Radioisotopes | doi.org/10.13182/NT05-A3624
A Numerical Model Without Truncation Error for a Steady-State Analysis of a Once-Through Steam Generator
Yoon Sub Sim, Eui Kwang Kim, Jae Hyuk Eoh
Nuclear Technology | Volume 150 | Number 3 | June 2005 | Pages 315-324
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT05-A3625
