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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
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Reliability Prediction of Passive Systems Based on Bivariate Probability Distributions
Luciano Burgazzi
Nuclear Technology | Volume 161 | Number 1 | January 2008 | Pages 1-7
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3908
Numerical Benchmarks for Very High-Temperature Reactors Based on the CNPS Critical Experiments
Hyung-Kook Joo, Temitope A. Taiwo, Won Sik Yang, Hussein S. Khalil
Nuclear Technology | Volume 161 | Number 1 | January 2008 | Pages 8-26
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3909
Dosimetric Management During a Criticality Accident
L. Lebaron-Jacobs, R. Fottorino, F. Barbry, P. Berard, F. Briot, P. Boisson, D. Cavadore, C. Challeton-de Vathaire, S. Distinguin, L. Exmelin, A. Flury-Herard, E. Gaillard-Lecanu, M. Gonin, J.-P. Le Goff, G. Lecoix, G. Lemaire, R. Medioni, M. H. Persico, Y. Racine, C. Riasse, E. Rongier, P. Voisin, A. Miele
Nuclear Technology | Volume 161 | Number 1 | January 2008 | Pages 27-34
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3910
French and United Kingdom Experience of High-Burnup Mixed-Oxide Fuel in Sodium-Cooled Fast Breeder Reactors
Philippe Martin, Michel Pelletier, Denis Every, Derek Buckthorpe
Nuclear Technology | Volume 161 | Number 1 | January 2008 | Pages 35-44
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3911
An Investigation of the Particle Size Responses for Various Fuel-Coolant Interactions in the TROI Experiments
I. K. Park, J. H. Kim, S. H. Hong, B. T. Min, S. W. Hong, J. H. Song, H. D. Kim
Nuclear Technology | Volume 161 | Number 1 | January 2008 | Pages 45-56
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3912
Lumped-Refined Multichannel Calculation Scheme for a High-Fidelity Thermal-Hydraulic Analysis by a Neutronics Code Coupling
Jin-Young Cho, Jae-Seung Song, Chung-Chan Lee, Sung-Quun Zee, Jae-Il Lee, Kil-Sup Um
Nuclear Technology | Volume 161 | Number 1 | January 2008 | Pages 57-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3913
Numerical Computation of Heat Transfer Enhancement of a PWR Rod Bundle with Mixing Vane Spacers
Wang-Kee In, Tae-Hyun Chun, Chang-Hwan Shin, Dong-Seok Oh
Nuclear Technology | Volume 161 | Number 1 | January 2008 | Pages 69-79
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3914
The Impact of Severe Accident Management Guidance on the Frequency of Containment Failure Modes of a Boiling Water Reactor
Kuan-Fu Chen, Ching-Hui Wu, Min Lee
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 81-97
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3915
Effect of the Surveillance Test Frequency of SDS1 on the Core Damage Probability
Sungwhan Cho, Jin Jiang
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 98-107
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3916
Core-Wide (In-Phase) Stability of Supercritical Water-Cooled Reactors - I: Sensitivity to Design and Operating Conditions
Jiyun Zhao, Pradip Saha, Mujid S. Kazimi
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 108-123
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3917
Core-Wide (In-Phase) Stability of Supercritical Water-Cooled Reactors - II: Comparison with Boiling Water Reactors
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 124-139
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3918
Impact of Spatial Heterogeneity of Source Term in Near-Surface Repository on Releases to Groundwater Pathway
Povilas Poskas, Raimondas Kilda, Valdas Ragaisis, Terry M. Sullivan
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 140-155
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT08-A3919
Long-Term Safety Assessment of a (Near-Surface) Short-Lived Radioactive Waste Repository in Lithuania
J. Mazeika, R. Petrosius, V. Jakimaviciute-Maseliene, D. Baltrunas, K. Mazeika, V. Remeikis, T. Sullivan
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 156-168
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT08-A3920
Corrosion Resistance of Amorphous Fe49.7Cr17.7Mn1.9Mo7.4W1.6B15.2C3.8Si2.4 Coating: A New Criticality Control Material
J. C. Farmer, J.-S. Choi, C.-K. Saw, R. H. Rebak, S. D. Day, T. Lian, P. D. Hailey, J. H. Payer, D. J. Branagan, L. F. Aprigliano
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 169-189
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A3921
Plutonium Release Fractions from Accidental Fires
Vladimir Kogan, Philip M. Schumacher
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 190-202
Technical Note | Miscellaneous | doi.org/10.13182/NT08-A3922
Development of Parameter-Identification Capability for MAAP4 Code
Chun-Sheng Chien, Shih-Jen Wang, Show-Chyuan Chiang
Nuclear Technology | Volume 161 | Number 3 | March 2008 | Pages 203-209
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3923
In-Vessel Retention of Molten Corium: Lessons Learned and Outstanding Issues
J. L. Rempe, K. Y. Suh, F. B. Cheung, S. B. Kim
Nuclear Technology | Volume 161 | Number 3 | March 2008 | Pages 210-267
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3924
Turbulence Model Assessment for Flow Across a Row of Confined Cylinders
Joshua Hodson, Robert Spall, Barton Smith
Nuclear Technology | Volume 161 | Number 3 | March 2008 | Pages 268-276
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3925
Performance Assessment of the Two-Phase Pump Degradation Model in the RELAP5-3D Transient Safety Analysis Code
Jeffrey W. Lane, L. E. Hochreiter, D. L. Aumiller, Jr., R. J. Kushner
Nuclear Technology | Volume 161 | Number 3 | March 2008 | Pages 277-285
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3926
A New Heat Transfer Correlation for Condensation in the Presence of Air and Its Implementation into RELAP5/MOD3.3
Fahri Aglar, Ali Tanrikut
Nuclear Technology | Volume 161 | Number 3 | March 2008 | Pages 286-298
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3927
Introduction of IDINHX, A New Heat Exchanger for Passive Decay Heat Removal
Yoon Sub Sim
Nuclear Technology | Volume 161 | Number 3 | March 2008 | Pages 299-314
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3928
Feasibility of Lead-Bismuth-Cooled Accelerator-Driven System for Minor-Actinide Transmutation
K. Tsujimoto, H. Oigawa, K. Kikuchi, Y. Kurata, M. Mizumoto, T. Sasa, S. Saito, K. Nishihara, M. Umeno, H. Takei
Nuclear Technology | Volume 161 | Number 3 | March 2008 | Pages 315-328
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT08-A3929
