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Prediction of Flooding Characteristic in Pulsed Disc and Doughnut Extraction Column Using LASSO Method Nucl. Technol. (IF 1.5) Pub Date : 2024-03-14 Lei Jin, Hui He, Yu Zhou, Hongguo Hou, Meng Zhang, Yang Gao
For achieving high separation efficiency and a large throughput in the nuclear fuel reprocessing industry, it is crucial to have a profound understanding of the flooding characteristics in pulsed d...
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Characterization of a Fast Neutron Irradiation Facility Using a Stilbene Scintillation Detector Nucl. Technol. (IF 1.5) Pub Date : 2024-03-15 Felix Pino, Jessica C. Delgado, Matteo Polo, Erica Fanchini, Anna Selva, Joana Minga, Gianmarco Torilla, Lodovico Ratti, Sandra Moretto
This paper describes the characterization of a fast neutron facility located at Legnaro National Laboratories’ Van de Graaff CN accelerator. The neutron flux is produced by the 9Be(p,xn) reactions...
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Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister-Filling Process: Part 1 Nucl. Technol. (IF 1.5) Pub Date : 2024-03-13 Simon Chung, Martin Stewart, Andrew Grima, Peter Wypych, Sam Moricca
In preliminary engineering studies and equipment commissioning, readily available simulants with certain resemblances to the target waste, such as particle size, may be employed. However, for the v...
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Elastic, Anelastic, and Thermal Properties of P91 Steel with Microstructural Variability Nucl. Technol. (IF 1.5) Pub Date : 2024-03-13 Z. Miles, A. Balodini, T. Seuaciuc-Osorio, J. J. Wall, M. Guimaraes, A. Zevalkink, S. K. Chakrapani
Grade 91 steel has been used in nuclear and fossil power plants since the 1970s. Manufacturing variabilities resulting from manufacturing, repair, and management activities have been attributed to ...
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Thermal and Electrical Performance Analyses of a 100-W Radioisotope Thermoelectric Generator for Space Exploration Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Shiping Wei, Jin Wang, Zhixin Ma, Ming Jin, Chunjing Li, Yuan Hu
A 100-W radioisotope thermoelectric generator (RTG) is by far the most suitable power supply for long-term deep space exploration where solar power would not be feasible. Understanding the thermal ...
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Temperature-Dependent Swelling in Helium Ion Irradiated Vanadium Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Weiping Zhang, Yiheng Chen, Wenrui Cheng, Liping Guo, FengFeng Luo
Vanadium is a typical low-activation metal and has the advantages of lower neutron irradiation activation, better mechanical properties at high temperature, and higher compatibility with the liquid...
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Simulation of Readout Electronics for Nuclear Radiation Detector Using MATLAB Program Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Jamal-Eddin Assaf, Zuheir Ahmad
A computer program was developed using the MATLAB programming language to simulate the electronics readout for a radiation detector system. The function of each stage of this system is described by...
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Methodology to Assist in Training Maneuvers of Operation of Pumps of a Nuclear Plant Using Virtual Reality Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Daniel Mól Machado, Gustavo Souza Pinheiro dos Santos, Andre Cotelli do Espirito Santo, Antonio Carlos de Abreu Mól, Celso Marcelo Franklin Lapa, Claudio Henrique dos Santos Grecco
In power plants, one of the important maneuvers is the switching of pumps, where incorrect execution can even cause the unit to shut down. Therefore, the objective of this paper is to create a virt...
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Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Kazuya Ohgama, Taira Hazama, Hiroki Katagiri, Atsushi Takegoshi, Tetsuya Mouri
In the prototype fast breeder reactor Monju, reaction rate distributions of the fission reaction rates of 239Pu, 235U, and 238U and the capture reaction rate of 238U were measured using activation ...
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Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Annie Berens, Nicholas Meehan, Mason Fox, Isabelle Lindsay, Nicholas R. Brown
High-temperature, gas-cooled reactors (HTGRs) are promising advanced reactor designs. Leveraging passive safety features, higher core outlet temperatures, previous commercial operational experience...
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Foreword: Special issue on Heavy Liquid Metal–Cooled Fast Reactor Technology Nucl. Technol. (IF 1.5) Pub Date : 2024-03-08 Mariano Tarantino, Giacomo Grasso, Pierdomenico Lorusso, Kamil Tuček
Published in Nuclear Technology (Vol. 210, No. 4, 2024)
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Measurement of Aerosol Transmission Through a Stress Corrosion Crack–Like Geometry Nucl. Technol. (IF 1.5) Pub Date : 2024-03-07 Samuel Durbin, Ramon Pulido, Philip Jones, Adrian Perales
The formation of a stress corrosion crack (SCC) in the canister wall of a dry cask storage system (DCSS) has been identified as a potential issue for the long-term storage of spent nuclear fuel. Th...
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Asymmetric Two-Step Thermosiphon for Containment Cooling of Small Modular Reactors Nucl. Technol. (IF 1.5) Pub Date : 2024-03-06 Sung-Jae Yi, Jin-Hwa Yang, Byong Guk Jeon, Hwang Bae, Hyun-Sik Park, Kwang-Won Seul
A thermosiphon is a heat transfer device that utilizes the phase change of a liquid and has a single closed-loop shape in a gravity-dominant field. This can be expressed as a single-step thermosiph...
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Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle Nucl. Technol. (IF 1.5) Pub Date : 2024-03-06 Xuyao Geng, Jie Wang
Microreactors comprise a new actively developing class of very small advanced reactors that have the potential to be an alternative to carbon-intensive energy technologies. A microreactor based on ...
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Investigating the Impact of UV-C Radiation on the Mechanical Characteristics of Semifinished Potato Tubers Prepared from Varied Potato Cultivars Nucl. Technol. (IF 1.5) Pub Date : 2024-03-06 Addis Lemessa Jembere, Tomasz Jakubowski
The relationship between various characteristics of postharvest vegetables and their corresponding biological surface properties is strongly interconnected, leading to a broad spectrum of propertie...
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i-LAMP: Global, Industrywide Learning Aging Management Program for Neutron-Absorber Materials in Spent Fuel Pools Nucl. Technol. (IF 1.5) Pub Date : 2024-03-06 Hatice Akkurt
Neutron-absorber materials are used in spent fuel pool (SFP) storage racks to increase storage capacity while maintaining criticality safety margins. Previously, the Electric Power Research Institu...
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Retention of Hydrogen Bubbles Generated from Water Radiolysis in Carbonate Slurry Nucl. Technol. (IF 1.5) Pub Date : 2024-03-04 Tatsuya Ito, Ryuji Nagaishi, Ryo Kuwano
The retention of hydrogen (H2) bubbles generated by water radiolysis was quantitatively studied in a high-viscous suspension of carbonate slurry consisting of a mixture of suspended solid (SS) of m...
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Sorption of U(VI) on MX-80 Bentonite and Granite in Ca-Na-Cl Saline Solutions Nucl. Technol. (IF 1.5) Pub Date : 2024-02-29 Zhiwei Zheng, Fabiola Guido Garcia, Jianan Liu, Shinya Nagasaki, Tammy (Tianxiao) Yang
Uranium has been identified as an element of interest for the safety assessment of a deep geological repository for used nuclear fuel. This paper examines the sorption behavior of U(VI) onto MX-80 ...
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In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis Nucl. Technol. (IF 1.5) Pub Date : 2024-02-28 Mark Schvaneveldt, Tyler Williams, Ranon Fuller, Devin Rappleye
Chloride volatility processes for purifying actinide and rare earth elements have historically required the use of Cl2 tanks. To minimize the hazards associated with these processes, an apparatus w...
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A Framework to Assess Advanced Reactor Spent Fuel Management Facility Deployment Nucl. Technol. (IF 1.5) Pub Date : 2024-02-28 Milos I. Atz, Robert A. Joseph, Edward A. Hoffman
Advanced nuclear reactors offer various operational advantages over existing light water reactors but could produce types of spent nuclear fuel (SNF) with a wide variety of forms and characteristic...
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Multicriteria Decision Making in Site Selection for Nuclear Power Plants Nucl. Technol. (IF 1.5) Pub Date : 2024-02-26 Berna Tuncer, Aysen D. Akkaya, M. Semih Yucemen
Nuclear energy is an important alternative energy source. However, construction of nuclear power plants (NPPs) requires the consideration of environmental, economic, socioeconomic, health, and safe...
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Computation of Particulate Deposition on Dry Storage Canisters Nucl. Technol. (IF 1.5) Pub Date : 2024-02-22 Sarah R. Suffield, Ben J. Jensen, Philip J. Jensen, William A. Perkins, Brady D. Hanson, Steven B. Ross, Christopher L. Grant, Casey J. Spitz
This paper provides an overview of ongoing work aimed at developing spent nuclear fuel (SNF) canister deposition models. Currently, it is known that stainless steel canisters are susceptible to chl...
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Modeling Microreactor Requirements for High-Performance Computing Nucl. Technol. (IF 1.5) Pub Date : 2024-02-23 Alvin J. H. Lee, Lucas Wodrich, Dimitri Kalinichenko, Caleb S. Brooks, Tomasz Kozlowski
The potential deployment of microreactors as a zero-emission source for critical applications within integrated energy systems such as microgrids has been gaining interest in recent years owing to ...
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Safeguards and Security for High-Burnup TRISO Pebble Bed Spent Fuel and Reactors Nucl. Technol. (IF 1.5) Pub Date : 2024-02-22 Charles Forsberg, Andrew Kadak
Several high-temperature thermal neutron–spectrum pebble bed reactors are being commercialized. China has started up two helium-cooled pebble bed high-temperature reactors. In the United States, th...
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Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates Nucl. Technol. (IF 1.5) Pub Date : 2024-02-22 Ben Lindley
Increasing the number of pins within a pressurized water reactor (PWR) assembly reduces pin temperature for a given assembly power. In conjunction with a core retrofit, this presents a potential ro...
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Effect of Gamma Heating on Heat Pipe–Cooled, Calcium Hydride–Moderated Core Nucl. Technol. (IF 1.5) Pub Date : 2024-02-20 Rei Kimura, Kazuhito Asano
A novel microreactor, called MoveluXTM, was previously proposed that utilizes heat pipes as the primary heat transfer device and calcium hydride as the moderator. In this core design, the moderator...
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Observations of Atmospheric Corrosion Testing on Heated Austenitic Stainless Steel Surfaces: Exploring the Role of Inert Dust Particulates and Seawater Nucl. Technol. (IF 1.5) Pub Date : 2024-02-20 R. F. Schaller, J. Snow, M. Maguire, L. Lemieux, R. M. Katona, J. Taylor, A. Knight, C. R. Bryan
Relevant atmospheric corrosion laboratory testing environments were developed to explore the influence of inert dust and seawater on the corrosion susceptibility of stainless steel in spent nuclear...
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Bentonites as Natural Sources of Thorium and Uranium Nucl. Technol. (IF 1.5) Pub Date : 2024-02-15 Javiera Cervini-Silva
Bentonites are natural reservoirs of various elements and are of interest because they are sources of thorium and uranium, which are transition elements that provide nuclear energy. The objective o...
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Key Technologies for Korean Space Heat Pipe Reactor Nucl. Technol. (IF 1.5) Pub Date : 2024-02-15 Byung Ha Park, Chan Soo Kim, Sung Hoon Choi, Sung Nam Lee
Sustainable energy is crucial for long-term space missions. Fission surface power is a leading option due to its ability to provide consistent electricity and heat irrespective of the sun’s positio...
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Assessing the Consequences of Postclosure Criticality in Spent Nuclear Fuel Nucl. Technol. (IF 1.5) Pub Date : 2024-02-09 Laura Price, Halim Alsaed, Eduardo Basurto, Alex Salazar, Gregory Davidson, Mathew Swinney
The U.S. Department of Energy is funding research into studying the consequences of postclosure criticality on the performance of a generic repository by (1) identifying the features, events, and p...
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TRACE Assessment for Simulating Density Wave Oscillations in a Full-Scale BWR Rod Bundle Under Natural Circulation Nucl. Technol. (IF 1.5) Pub Date : 2024-02-09 Paul Hurley, Connor Pigg, Yang Liu, Tomasz Kozlowski, Juliana Pacheco Duarte
Density wave oscillation (DWO) is one of the most extensively studied dynamic two-phase flow instabilities. The accurate prediction of these phenomena is important to ensuring safety in two-phase f...
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Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor Nucl. Technol. (IF 1.5) Pub Date : 2024-02-09 Melissa Moreno, Danielle Redhouse, Christopher Perfetti
The Annular Core Research Reactor (ACRR) Monte Carlo N-Particle (MCNP) model is used by ACRR reactor operators and experiment designers at Sandia National Laboratories for a variety of computationa...
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Boiling and Drying Accident of High-Level Liquid Waste in a Reprocessing Plant: Examination of the Time-Dependent Temperature Increase of the Waste and of the Generation Rates of the Individual Components Released into the Gas Phase Nucl. Technol. (IF 1.5) Pub Date : 2024-02-12 Takashi Kodama, Hiroshi Kinuhata, Mikio Kumagai, Kazunori Suzuki, Shin-Itiro Hayashi, Shingo Matsuoka
Using the amount, composition, and decay power density of high-level liquid waste in a storage tank, the temperature change of the waste up to 600°C and the corresponding vapor and gas release rate...
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Designing Nuclear Fuels with a Multi-Principal Element Alloying Approach Nucl. Technol. (IF 1.5) Pub Date : 2024-02-07 G. Beausoleil, J. Zillinger, L. Hawkins, T. Yao, A. G. Weiss, X. Pu, N. Jerred, D. Kaoumi
Previous research has shown that multi-principal element alloys (MPEAs) using chromium, molybdenum, niobium, tantalum, titanium, vanadium, and zirconium can form stable body-centered-cubic (BCC) st...
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Comments on the Frisch-Peierls Estimate of the Critical Mass of a Uranium Fission Bomb Nucl. Technol. (IF 1.5) Pub Date : 2024-02-01 J. M. Pearson
The Frisch-Peierls memorandum of March 1940 opened the way to nuclear weapons through its conclusion that the critical mass for an explosive chain reaction in 235U could be as small as 0.6 kg. This...
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Development of a Surrogate System of a Plant Dynamics Simulation Model and an Abnormal Situation Identification System for Nuclear Power Plants Using Deep Neural Networks Nucl. Technol. (IF 1.5) Pub Date : 2024-02-01 Akiyuki Seki, Masanori Yoshikawa, Ryota Nishinomiya, Shoichiro Okita, Shigeru Takaya, Xing Yan
In the case of a new nuclear reactor, existing evaluation experience is limited; thus, accidents and troubles may occur as a result of such lack of experience. To deal with such situations, it is d...
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Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh Nucl. Technol. (IF 1.5) Pub Date : 2024-02-01 Jung-Kun Lee, Sumin Bae, Sajib A. Dahr
Lead-cooled fast reactor (LFR) technology offers technical benefits such as high temperature operation, virtually no loss of coolant accidents, and operation at atmospheric pressure. Liquid lead is...
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CFD Modeling and Analysis of a Heat-Generating Melt Pool Under External Vessel Cooling and Top Flooding Nucl. Technol. (IF 1.5) Pub Date : 2024-01-26 Samyak S. Munot, Arun K. Nayak, Jyeshtharaj B. Joshi
In some nuclear reactors, under accidental conditions, core debris forms a molten pool, which is later located in a core catcher. The core catcher proposed by the authors uses special refractory ma...
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Foreword: Special issue on the Power-to-Melt and Maneuverability (P2M) Simulation Exercise Nucl. Technol. (IF 1.5) Pub Date : 2024-01-18 Guest Editor Jerome Sercombe
Published in Nuclear Technology (Vol. 210, No. 2, 2024)
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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 Nucl. Technol. (IF 1.5) Pub Date : 2024-01-18 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
To refine knowledge about pressurized water reactor fuel melting, the Power to Melt and Maneuverability (P2M) project in the Framework for Irradiation Experiments II (FIDES-II) managed by the Nucle...
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The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program Nucl. Technol. (IF 1.5) Pub Date : 2024-01-18 G. Bonny, P. Blanpain, D. Rozzia, S. Billiet, M. Verwerft, B. Boer
In this work, a detailed reevaluation of a past power-to-melt experiment performed within the so-called High Burnup Chemistry project is provided. A pressurized water reactor–type UO2 fuel rod was ...
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Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE Nucl. Technol. (IF 1.5) Pub Date : 2024-01-18 V. D’Ambrosi, J. Sercombe, S. Béjaoui, I. Zacharie-Aubrun, C. Introïni, J. Karlsson, D. Jädernäs, H.-U. Zwicky
This paper presents simulations of the xM3 power ramp with the fuel performance code ALCYONE performed during an international simulation exercise organized within the Organisation for Economic Co-...
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Issues Associated with Yellow Phase Formation and Other Disruptions in Japanese High-Level Waste Vitrification and Their Improvement Nucl. Technol. (IF 1.5) Pub Date : 2023-12-15 Akira Sakai, Siegfried Weisenburger, Ian L. Pegg, Shuichi Ishida
The Rokkasho Reprocessing Plant, located in northern Japan, includes facilities for reprocessing spent nuclear fuels and immobilizing high-level waste (HLW) into a stable-glass waste form based on ...
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A Pressure Drop and Particle Image Velocimetry Investigation into Depressurized Loss-of-Coolant Accident Parameters Applied to Packed Beds with an Aspect Ratio of D/dp = 4.4 Nucl. Technol. (IF 1.5) Pub Date : 2023-12-14 Stephen King, Thien Nguyen, Yassin Hassan
New developments in porous media modeling have allowed for a new opportunity to implement experimental data for validation and verification. This includes velocity measurements using particle image...
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An Assessment of Deep Borehole Disposal Post-Closure Safety Nucl. Technol. (IF 1.5) Pub Date : 2023-12-15 Dirk Mallants, Julien Bourdet, Michael Camilleri, Punjehl Crane, Claudio Delle Piane, Alec Deslandes, Dave Dewhurst, Christian Doblin, Hans-Joachim Engelhardt, Lionel Esteban, Tilman Fischer, Ema Frery, Christoph Gerber, Matthew Josh, Uli Kelka, Manoj Khanal, Laurent Langhi, Kaveh Sookhak Lari, Thomas Poulet, Matthias Raiber, Regina Sander, Mustafa Sari, Joel Sarout, Peter Schaubs, Heather Sheldon
Around the world, deep borehole disposal is being evaluated for intermediate level-waste (ILW), high-level waste, and spent nuclear fuel. To facilitate a disposal concept options analysis for ILW i...
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Technical Reviewers Nucl. Technol. (IF 1.5) Pub Date : 2023-12-13
Published in Nuclear Technology (Vol. 210, No. 1, 2024)
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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 Nucl. Technol. (IF 1.5) Pub Date : 2023-12-01 Ryo Yokoyama, Masahiro Kondo, Shunichi Suzuki, Christophe Journeau, Marco Pellegrini, Koji Okamoto
Accomplishing the retrieval of fuel debris from Fukushima Daiichi Nuclear Power Plant (1F) Unit 3 (1F3) requires an understanding of its distribution. In this study, we performed real-scale corium ...
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Current Progress on the Development of the Integrated Waste Management Consent-Based Siting Process in the United States Nucl. Technol. (IF 1.5) Pub Date : 2023-11-08 J. Uribe, N. Saraeva, K. Petry, E. Bickford, R. Kreuzer, R. Howard
Consent-based siting is an approach to siting facilities that prioritizes the participation and needs of people and communities and seeks their willing and informed consent to accept a project in t...
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Foreword: Selected papers from the 12th Japan-U.S. Seminar on Two-Phase Flow Dynamics Nucl. Technol. (IF 1.5) Pub Date : 2023-11-09 Steven Ceccio, Yuichi Murai, Xiaodong Sun, Shuichiro Miwa
Published in Nuclear Technology (Vol. 209, No. 12, 2023)
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Quantitative Validation of Gas-Liquid Flow Regime Transition Using Eulerian-Eulerian CFD Models Nucl. Technol. (IF 1.5) Pub Date : 2023-11-09 J. R. Buchanan Jr., C. E. Clifford, B. M. Waite, T. S. Worosz, M. D. Zimmer
Quantitative validation of a computational fluid dynamics (CFD) code is about making point-to-point comparisons over fields of data to make statements about predictive fidelity. By the very nature ...
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Status of the Site Investigation and Site Selection Process for a Deep Geological Repository in Switzerland Nucl. Technol. (IF 1.5) Pub Date : 2023-11-08 Herwig R. Müller, Ingo Blechschmidt, Stratis Vomvoris, Tim Vietor, Maurus Alig, Matthias Braun
Nagra, the National Cooperative for the Disposal of Radioactive Waste, in Switzerland, is realizing a project of the century: the planning, construction, operation, and closure of a deep geological...
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Package Performance Study: A Historical Perspective and Planning for a Path Forward Nucl. Technol. (IF 1.5) Pub Date : 2023-10-30 Laura Hay, Steven Maheras, Erica Bickford, Matthew Feldman, Douglas Ammerman
The topic of spent nuclear fuel (SNF) transportation often draws public attention and concerns regarding safety, and with large-scale shipping campaigns expected in the future, public interest is a...
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Modeling Geologic Waste Repository Systems Below Residual Saturation Nucl. Technol. (IF 1.5) Pub Date : 2023-10-24 Matthew J. Paul, Heeho D. Park, Michael Nole, Scott L. Painter
The heat generated by high-level radioactive waste can pose numerical and physical challenges to subsurface flow and transport simulators if the liquid water content in a region near the waste pack...
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Commentary Nucl. Technol. (IF 1.5) Pub Date : 2023-10-10 Andrew C. Klein
Published in Nuclear Technology (Vol. 209, No. 11, 2023)
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REMADA: An Emergency Decision-Making Software for Radiation Dose Estimation of Mitigation Tasks in a Reactor Building During Severe Nuclear Accidents Nucl. Technol. (IF 1.5) Pub Date : 2023-10-13 Chunsen Shi, Jun Li, Jianxiang Zheng, Jian Zhang, Liuxuan Cao, Huifang Miao
In the event of a postulated severe accident, fission products may leak into the reactor building through the containment wall, exerting a radiological impact on the emergency response team as they...
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A Semi-Empirical Correlation for the Onset of Density Wave Oscillations in a Helical Coil Steam Generator Nucl. Technol. (IF 1.5) Pub Date : 2023-10-13 José N. Reyes Jr.
NuScale Power has completed a series of full-length helical coil steam generator tests at SIET Laboratories in Piacenza, Italy. The test program included an investigation of the onset and evolution...
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Exhaustive Test Case Generation for Nuclear Safety Software Based on the Software Logic Model Nucl. Technol. (IF 1.5) Pub Date : 2023-10-12 Sang Hun Lee, Seung Jun Lee, Sung Min Shin, Eun-Chan Lee, Hyun Gook Kang
An issue regarding the incorporation of software reliability within the nuclear power plant (NPP) probabilistic risk assessment model has emerged in the licensing processes of digitalized NPPs. Sin...
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Artificial Intelligence Detection System of Radioactive Nanocomposites in Liquid-Filled Containers for Nuclear Security Nucl. Technol. (IF 1.5) Pub Date : 2023-10-10 Elham Gharibshahi, Miltos Alamaniotis
Nuclear terrorism resulting from the illicit trafficking of nuclear and radioactive materials consists of a serious threat against the security of countries. Hence, the transportation of hidden nuc...
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Foreword: Selected papers from the 17th International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2021) Nucl. Technol. (IF 1.5) Pub Date : 2023-10-10 Guest Editor Carol Smidts
Published in Nuclear Technology (Vol. 209, No. 11, 2023)
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Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625 Nucl. Technol. (IF 1.5) Pub Date : 2023-10-10 V. O’Donnell, X. He, T. Keya, G. Harvill, M. Andurkar, B. C. Prorok, S. M. Thompson, J. Gahl
A point of study in the characterization of additive manufactured (AM) alloys is whether or not AM microstructure responds to external stimuli differently from conventionally manufactured alloys. S...