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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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Simulation of the NuScale SMR and Investigation of the Effect of Load-Following on Component Lifetimes
Una Baker, Marisol Garrouste, Sooyoung Choi, Gabriel J. Soto, Ross Snuggerud, Brendan Kochunas, Ben Lindley
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 1-22
Research Article | doi.org/10.1080/00295450.2023.2216973
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix
C. Colterjohn, S. Nagasaki, Y. Fujii
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 23-45
Research Article | doi.org/10.1080/00295450.2023.2217390
Experimental Simulation of Decay Heat of Corium at the Lava-B Test-Bench
M. K. Bekmuldin, М. K. Skakov, V. V. Baklanov, А. V. Gradoboev, A. S. Akayev, K. O. Toleubekov
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 46-54
Research Article | doi.org/10.1080/00295450.2023.2226539
Estimation Method for Residual Sodium Amount on Unloaded Dummy Fuel Assembly
Munemichi Kawaguchi, Yasushi Hirakawa, Yusuke Sugita, Yutaka Yamaguchi
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 55-71
Research Article | doi.org/10.1080/00295450.2023.2214261
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment
H. Ziani, T. El Bardouni, C. Elyounoussi, I. Berriban, T. El Ghalbzouri, B. El Bakkari, O. El Hajjaji, S. ElMaliki ElHlaibi, M. Lahdour, H. El Yaakoubi
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 72-83
Research Article | doi.org/10.1080/00295450.2023.2216452
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling
Philseo Kim, Man-Sung Yim, Justin V. Hastings, Philip Baxter
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 84-99
Research Article | doi.org/10.1080/00295450.2023.2218241
Sequential Deployment of Mobile Radiation Sensor Network Using Reinforcement Learning in Radioactive Source Search
Siyao Gu, Miltiadis Alamaniotis
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 100-111
Research Article | doi.org/10.1080/00295450.2023.2226914
Detecting Anomalies in Simulated Nuclear Data Using Autoencoders
Pedro Mena, R. A. Borrelli, Leslie Kerby
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 112-125
Research Article | doi.org/10.1080/00295450.2023.2214257
Optimized FSF Controller for Bulk Power Control of Large-Core PHWRs
P. D. Vaswani, P. K. Tamboli, Debraj Chakraborty
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 126-136
Research Article | doi.org/10.1080/00295450.2023.2214662
Cherenkov Glass Detectors with Wavelength Shifting Fibers for Neutron Measurements
Hattan Natto, Haori Yang
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 137-146
Research Article | doi.org/10.1080/00295450.2023.2217058
Performance Evaluation of Batchwise Multistage Countercurrent Extraction in a LiCl–KCl/Cd System to Separate Actinides from Rare Earth Fission Products
Yoshiharu Sakamura
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 147-164
Research Article | doi.org/10.1080/00295450.2023.2216974
One-Dimensional Steady-State Thermal Model of CNTP Reactor
Jacob Keese, D. Keith Hollingsworth
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 165-179
Research Article | doi.org/10.1080/00295450.2023.2216989
Geant4 Extension for Neutronic Calculation of Nuclear Reactor Core
Hossein Hashemi-Jozani, Khalil Moshkbar-Bakhshayesh, Soroush Mohtashami, Behzad Rokhbin
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 180-188
Note | doi.org/10.1080/00295450.2023.2224131
P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments
V. D’Ambrosi, J. Sercombe, S. Bejaoui, A. Chaieb, B. Baurens, R. Largenton, A. Ambard, B. Boer, G. Bonny, M. Ševeček, L. E. Herranz, F. Feria Marquez, K. Inagaki, H. Ohta, F. Boldt, J. Sappl, R. Armstrong, A. Mohamad, Y. Udagawa, C. Cozzo, J. Klouzal, M. Vitezslav, J. Corson, J. Peltonen
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 189-215
Research Article | doi.org/10.1080/00295450.2023.2194270
The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program
G. Bonny, P. Blanpain, D. Rozzia, S. Billiet, M. Verwerft, B. Boer
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 216-231
Research Article | doi.org/10.1080/00295450.2023.2264505
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code CYRANO3
A. Chaieb, R. Largenton, A. Ambard, B. Baurens, M. Ton That
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 232-244
Research Article | doi.org/10.1080/00295450.2023.2232664
Modeling of the P2M Past Fuel Melting Experiments with the FEMAXI-8 Code
Afiqa Mohamad, Yutaka Udagawa
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 245-260
Research Article | doi.org/10.1080/00295450.2023.2185061
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1
James Corson, Alice Chung, Steven Muller
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 261-268
Research Article | doi.org/10.1080/00295450.2023.2181042
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE
J. Sercombe, V. D’Ambrosi, S. Béjaoui, I. Zacharie-Aubrun
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 269-284
Research Article | doi.org/10.1080/00295450.2023.2188138
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE
V. D’Ambrosi, J. Sercombe, S. Béjaoui, I. Zacharie-Aubrun, C. Introïni, J. Karlsson, D. Jädernäs, H.-U. Zwicky
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 285-307
Research Article | doi.org/10.1080/00295450.2023.2253660
Fuel Melting Simulation with FRAPCON/FRAPTRAN Codes for the Power-to-Melt-and-Maneuverability Simulation Exercise and Consideration of Model Modifications
Kenta Inagaki
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 308-323
Research Article | doi.org/10.1080/00295450.2023.2239041
Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code
D. Rozzia, G. Bonny, S. Billiet, B. Boer, M. Verwerft
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 324-353
Research Article | doi.org/10.1080/00295450.2023.2229186
Determination of the Gas Plenum Temperature of the P2M Instrumented Fuel Rodlets on the Basis of a Thermal-Hydraulic Study of the Belgian Reactor 2 Pressurized Water Capsule
A. Fayet, S. Béjaoui, T. Cadiou, J. Perez-Manes, E. Deveaux, A. Vernier, V. D’Ambrosi, J. Sercombe, C. Nonon-Solaro, G. Bignan, C. Koren, S. Mimouni, A. Ambard, B. Rossaert, P. Gouat, B. Boer, R. Wouter-Bosch
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 354-377
Research Article | doi.org/10.1080/00295450.2023.2271222
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys
Masrukan Masrukan, M. Husna Alhasa, Maman Kartaman, Juan Carlos Sihotang
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 379-390
Research Article | doi.org/10.1080/00295450.2023.2227814
Evaluation of Corrosion Behavior of Various Fe- and Ni-Based Alloys in Molten Li2BeF4 (FLiBe)
Krishna Moorthi Sankar, James R. Keiser, Dino Sulejmanovic, Tracie M. Lowe, Preet M. Singh
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 391-408
Research Article | doi.org/10.1080/00295450.2023.2229176
A Comprehensive Approach to Molten Salt Reactor Source Term Generation and Shielding Analyses
Kyle Carberry, Bojan Petrovic
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 409-435
Research Article | doi.org/10.1080/00295450.2023.2229181
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima
D. P. Dionizio, P. L. C. Saldanha, P. F. Frutuoso E Melo, C. M. F. Lapa
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 436-456
Research Article | doi.org/10.1080/00295450.2023.2229182
Numerical Investigation into the Temperature Profile of a PHWR Channel Containing a Disassembled Fuel Bundle During a Postulated Accident Condition
Ketan Ajay, Ravi Kumar, Akhilesh Gupta
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 457-470
Research Article | doi.org/10.1080/00295450.2023.2229190
Investigation on Residual Stress in SA508/Inconel Metal/CF8A Dissimilar Welded Joint for Nuclear Steam Generator Safe End Using Different Processes
Zhifang Gao, Lei Zhao, Yongdian Han
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 471-485
Research Article | doi.org/10.1080/00295450.2023.2229602
Pore Forming Agent–Assisted Fabrication of Porous Platinum Vent Frits and Their Suitability Evaluation for Radioisotope Power Sources
G. Singh, S. G. Mohod, P. V. S. Varma, P. Purohit, D. B. Sathe, R. B. Bhatt
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 486-500
Research Article | doi.org/10.1080/00295450.2023.2232224
Preparation and Performance of a Self-Brittle Corrosive Bifunctional Detergent for Corrosive Deep Decontamination of Stainless Steel Surface Based on Controlled Polymerization by the RAFT One-Pot Method
Yutuo Wang, Yintao Li, Zhengquan Zhang, Mengqing Xiao, Changwen Chen, Yuanlin Zhou, Shanqiang Wang
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 501-510
Research Article | doi.org/10.1080/00295450.2023.2232646
Designing Nuclear Fuels with a Multi-Principal Element Alloying Approach
G. Beausoleil, J. Zillinger, L. Hawkins, T. Yao, A. G. Weiss, X. Pu, N. Jerred, D. Kaoumi
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 511-531
Research Article | doi.org/10.1080/00295450.2023.2236796
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods
Vikram Rathore, Lorenzo Senis, Stefan Jarl Holm, Erik Andersson Sundén, Ane Håkansson, Mounia Laassiri, Peter Dendooven, Peter Andersson
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 532-541
Research Article | doi.org/10.1080/00295450.2023.2236882
Analysis and Preliminary Design of Primary Heat Exchanger Failure Testing Facility for Lead-Cooled Fast Reactors
Federico Hattab, Fabio Giannetti, Vincenzo Narcisi, Pierdomenico Lorusso, Filippo Bussoletti, Michael Epstein, Sung Jin Lee, Mariano Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 543-564
Research Article | doi.org/10.1080/00295450.2023.2173482
Steady-State and Transient Compliance of CIRCE-THETIS CFD Model
Manuela Profir, Vincent Moreau
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 565-578
Research Article | doi.org/10.1080/00295450.2023.2175589
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology
M. Caramello, M. Frignani, R. Beaumont, M. Tarantino, C. Stansbury, P. Ferroni
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 579-590
Research Article | doi.org/10.1080/00295450.2023.2181043
Thermal-Hydraulic Characterization and Numerical Modeling with RELAP5 Code of ATHENA Secondary Loop
Tommaso Del Moro, Fabio Giannetti, Mariano Tarantino, Pierdomenico Lorusso, Marco Caramello, Damiano Vitale Di Maio, Marin Constantin
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 591-607
Research Article | doi.org/10.1080/00295450.2023.2183025
Experimental Analysis of Steam Generator Tube Rupture in CIRCE Facility for MYRRHA Configuration
Alessio Pesetti, Mariano Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 608-628
Research Article | doi.org/10.1080/00295450.2023.2185050
Liquid-Metal Thermal-Hydraulic Numerical Analyses in Support of the Upcoming CIRCE-THETIS Experimental Campaign
Pietro Stefanini, Francesco Galleni, Ivan Di Piazza, Andrea Pucciarelli
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 629-643
Research Article | doi.org/10.1080/00295450.2023.2189892
Design and Assessment of the New CIRCE-THETIS Facility for the Development of Heavy Liquid Metal Cooled Fast Reactors
Pierdomenico Lorusso, Ivan Di Piazza, Daniele Martelli, Mariano Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 644-665
Research Article | doi.org/10.1080/00295450.2023.2189903
Westinghouse Test Facilities for Lead Fast Reactor Development
Sung Jin Lee, Michael Ickes, Jeffrey L. Arndt, Michael Epstein, Asfaq Patel, Paolo Ferroni
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 666-680
Research Article | doi.org/10.1080/00295450.2023.2197667
Flow-Induced Vibration Experiment in Fuel Pin Bundle with Heavy Liquid Metal Flow: Test Section Design and Measurement Methods
I. Di Piazza, D. Martelli, C. Carrelli, T. Rovai, V. Raschioni, M. Ramacciotti, A. Spezzaneve, D. Ferretti, G. Mongiardini
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 681-691
Research Article | doi.org/10.1080/00295450.2023.2203285
Multiscale Thermal-Hydraulic Analysis of the ATHENA Core Simulator
P. Cioli Puviani, I. Di Piazza, R. Marinari, R. Zanino, M. Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 692-712
Research Article | doi.org/10.1080/00295450.2023.2215682
Subchannel Analysis of LFR Wire-Wrapped Fuel Bundle with RELAP5-3D
Cristiano Ciurluini, Vincenzo Narcisi, Ivan Di Piazza, Fabio Giannetti
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 713-724
Research Article | doi.org/10.1080/00295450.2023.2222248
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment
Mariano Tarantino, Pierdomenico Lorusso, Alessio Pesetti, Ivan Di Piazza, Daniele Martelli
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 725-739
Research Article | doi.org/10.1080/00295450.2023.2226525
The Passive Heat Removal Facility: Testing and Demonstrating an Innovative Decay Heat Removal System
M. Caramello, M. Frignani, R. Beaumont, M. Tarantino, J. Liao, R. F. Wright, M. Durse, A. Wimshurst, P. Ferroni
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 740-757
Research Article | doi.org/10.1080/00295450.2023.2241731
Preliminary Characterization of Alumina-Forming Austenitic–Type Advanced Alloys as Structural Materials for LFRs
A. Meli, S. Bassini, C. Ciantelli, A. Fiore, M. Angiolini, M. Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 758-771
Research Article | doi.org/10.1080/00295450.2023.2257547
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh
Jung-Kun Lee, Sumin Bae, Sajib A. Dahr
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 772-780
Research Article | doi.org/10.1080/00295450.2023.2277027
Impact Analysis of a Commercial Airplane Over a Nuclear Spent Fuel Dry Storage Cask
Edgar Hernández-Palafox, Pablo Ruiz-López, Luis Héctor Hernández Gómez, Alejandra Armenta-Molina, Gilberto Soto-Mendoza, Juan Alfonso Beltrán-Fernández, Luis Alberto Arenas-Magos
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 781-794
Research Article | doi.org/10.1080/00295450.2023.2244314
Attractiveness of Fissile Material in Nuclear Wastes from Different Fuel Cycles
Milos I. Atz, Massimiliano Fratoni
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 795-813
Research Article | doi.org/10.1080/00295450.2023.2246736
Validation of the Hybrid Turbulence Model in Detailed Thermal-Hydraulic Analysis Code SPIRAL for Fuel Assembly Using Sodium Experiments Data of 37-Pin Bundles
Ryuji Yoshikawa, Yasutomo Imai, Norihiro Kikuchi, Masaaki Tanaka, Hiroyuki Ohshima
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 814-835
Research Article | doi.org/10.1080/00295450.2023.2249707
Construction of the Dynamic Model and Control System for the Canadian Supercritical Water–Cooled Reactor Power Plant
Huirui Han, Chao Zhang
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 836-849
Research Article | doi.org/10.1080/00295450.2023.2249710
Exhaustive Test Case Generation for Nuclear Safety Software Based on the Software Logic Model
Sang Hun Lee, Seung Jun Lee, Sung Min Shin, Eun-Chan Lee, Hyun Gook Kang
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 850-867
Research Article | doi.org/10.1080/00295450.2023.2250133
Artificial Intelligence Detection System of Radioactive Nanocomposites in Liquid-Filled Containers for Nuclear Security
Elham Gharibshahi, Miltos Alamaniotis
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 868-883
Research Article | doi.org/10.1080/00295450.2023.2254168
Evaluation of Molten Corium Spreading and Sedimentation Behaviors Within Primary Containment Vessel in Unit 3 of Fukushima Daiichi Nuclear Power Plant Toward the Best Prediction of Fuel Debris Distribution
Ryo Yokoyama, Masahiro Kondo, Shunichi Suzuki, Christophe Journeau, Marco Pellegrini, Koji Okamoto
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 884-905
Research Article | doi.org/10.1080/00295450.2023.2262255
A Semi-Empirical Correlation for the Onset of Density Wave Oscillations in a Helical Coil Steam Generator
José N. Reyes Jr.
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 906-918
Research Article | doi.org/10.1080/00295450.2023.2264475
REMADA: An Emergency Decision-Making Software for Radiation Dose Estimation of Mitigation Tasks in a Reactor Building During Severe Nuclear Accidents
Chunsen Shi, Jun Li, Jianxiang Zheng, Jian Zhang, Liuxuan Cao, Huifang Miao
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 919-932
Research Article | doi.org/10.1080/00295450.2023.2264515
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625
V. O’Donnell, X. He, T. Keya, G. Harvill, M. Andurkar, B. C. Prorok, S. M. Thompson, J. Gahl
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 933-940
Note | doi.org/10.1080/00295450.2023.2262265