JournalTOCs

Nuclear Technology
Journal Prestige (SJR): 0.828

Citation Impact (citeScore): 1
Number of Followers: 5

Hybrid journal * Containing 10 Open Access article(s) in this issue *
ISSN (Print) 0029-5450 - ISSN (Online) 1943-7471
Published by Taylor and Francis

[2652 journals]

Electron Target Cooling Analyses of the KIPT ADS Using MCNP and Ansys
Fluent
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  Authors: A. Talamo, Z. Zhong, Y. Gohar
  Pages: 1 - 32
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-30T07:46:56Z
  DOI: 10.1080/00295450.2023.2202790
Benchmarking Neutron Counting System for Passive Measurements and Active
Interrogation of Unknown Objects for Fissile and Fissionable Materials
Determination
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  Authors: Fawaz Ali, Ghaouti Bentoumi, Liqian Li, Ronald B. Rogge
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-23T07:55:40Z
  DOI: 10.1080/00295450.2023.2202793
P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments
Open Access Article
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  Authors: 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
  Pages: 1 - 27
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-23T06:46:40Z
  DOI: 10.1080/00295450.2023.2194270
Assessing the Structure-Based Turbulence Model Performance for Thermal
Striping Applications Using Symmetric Jet Experiments
Open Access Article
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  Authors: Monica Pham, Victor Petrov, Annalisa Manera, Emilio Baglietto
  Pages: 1 - 11
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-22T06:53:18Z
  DOI: 10.1080/00295450.2023.2204989
An Experimental Validation of Spectrally Matched Neutron Detection Systems
Using 3He and BF3
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  Authors: Codey Olson, Jesse Snow, Meng-Jen (Vince) Wang, Glenn Sjoden, Edward Cazalas
  Pages: 1 - 11
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-22T06:53:16Z
  DOI: 10.1080/00295450.2023.2203291
Analysis of the Neutron Radiographic Image Quality and Beam Intensity
Produced by a Compact Multichannel Collimator
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  Authors: Brock Jolicoeur, Norbert Hugger, David Medich
  Pages: 1 - 7
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-22T06:53:06Z
  DOI: 10.1080/00295450.2023.2204988
Flow Induced Vibration Experiment in Fuel Pin Bundle with Heavy
Liquid-Metal Flow: Test Section Design and Measurement Methods
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  Authors: I. Di Piazza, D. Martelli, C. Carrelli, T. Rovai, V. Raschioni, M. Ramacciotti, A. Spezzaneve, D. Ferretti, G. Mongiardini
  Pages: 1 - 11
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-18T06:34:01Z
  DOI: 10.1080/00295450.2023.2203285
Neutronic Performance Analysis of Inner-Side Chromium Coatings for
Accident Tolerant Fuel
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  Authors: Rofida Hamad Khlifa, Nicolay N. Nikitenkov
  Pages: 1 - 14
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-18T06:31:31Z
  DOI: 10.1080/00295450.2023.2203282
Assessment of Engineering Turbulence Models in Buoyant Diabatic Turbulent
Flow
Open Access Article
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  Authors: Ralph Wiser, Emilio Baglietto
  Pages: 1 - 24
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-17T03:08:10Z
  DOI: 10.1080/00295450.2023.2202802
Location and Activity Characterization of Gamma-Ray Point Sources
Concealed in Shipping Containers Using Iterative Reconstruction and
Modeling Cargo-Specific Attenuation
Open Access Article
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  Authors: Euan L. Connolly, Dean T. Connor, Peter G. Martin
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-16T02:37:48Z
  DOI: 10.1080/00295450.2023.2198473
Machine Learning Surrogates of a Fuel Matrix Degradation Process Model for
Performance Assessment of a Nuclear Waste Repository
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  Authors: Bert J. Debusschere, D. Thomas Seidl, Timothy M. Berg, Kyung Won Chang, Rosemary C. Leone, Laura P. Swiler, Paul E. Mariner
  Pages: 1 - 24
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-16T02:34:53Z
  DOI: 10.1080/00295450.2023.2197666
Thermal Assessment of Repository Footprint Requirement for Advanced Fuel
Cycles
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  Authors: Milos I. Atz, Massimiliano Fratoni
  Pages: 1 - 20
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-16T02:31:59Z
  DOI: 10.1080/00295450.2023.2189430
Experimental Study on Aerosol and Gas Emission of Solvent Fire Accident in
Nuclear Fuel Cycle Facility
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  Authors: Yiren Lian, Hongchao Sun, Hao Yang, Xiaopeng Song, Xinjing Yang, Shutang Sun, Pengyi Wang, Lei Chen, Yeming Zhu, Guoqiang Li, Jiangang Zhang
  Pages: 1 - 7
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-12T03:47:47Z
  DOI: 10.1080/00295450.2023.2200542
Removal Effectiveness for Washing Ce(IV), U(VI), and Zr(IV) Ions from
Contaminated Purex Solvent by Hydrazine Carbonate
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  Authors: Guanghui Wang, Hui He, Yaorui Li, Meng Zhang, Yang Gao, Caishan Jiao
  Pages: 1 - 9
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-12T03:43:45Z
  DOI: 10.1080/00295450.2023.2199905
A Better Method to Calculate Fuel Burnup in Pebble Bed Reactors Using
Machine Learning
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  Authors: Carlos X. Soto, Odera Dim, Yonggang Cui, Warren Stern
  Pages: 1 - 13
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-11T08:40:18Z
  DOI: 10.1080/00295450.2023.2200573
A CNN-LSTM–Based Model to Fault Diagnosis for CPR1000
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  Authors: Changan Ren, He Li, Jichong Lei, Jie Liu, Wei Li, Kekun Gao, Guocai Huang, Xiaohua Yang, Tao Yu
  Pages: 1 - 8
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-11T08:36:57Z
  DOI: 10.1080/00295450.2023.2199098
Spatiotemporal Evaluation of Bubble Characteristics in Sodium Using
Real-Time X-Ray Imaging
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  Authors: Avinash Kumar Acharya, E. Hemanth Rao, M. Menaka, Sanjay Kumar Das, D. Ponraju, B. Venkatraman
  Pages: 1 - 14
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-11T08:33:10Z
  DOI: 10.1080/00295450.2023.2199079
Liquid Film Thickness for Gas-Liquid Annular Flow Across Grid Spacer with
Vanes in Simple 3 × 3 Rod Bundle Channel
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  Authors: Akimaro Kawahara, Yukihiro Yonemoto, Hiroto Tazoe
  Pages: 1 - 15
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-11T08:09:05Z
  DOI: 10.1080/00295450.2023.2197944
Measurement of Local Void Fraction of Air Water Flow in the 8 × 8 Rod
Bundle Using High-Resolution Gamma-Ray Tomography
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  Authors: Taehwan Ahn, Julio Diaz, Robert Adams, Victor Petrov, Annalisa Manera
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-11T07:58:59Z
  DOI: 10.1080/00295450.2023.2197680
Westinghouse Test Facilities for Lead Fast Reactor Development
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  Authors: Sung Jin Lee, Michael Ickes, Jeffrey L. Arndt, Michael Epstein, Asfaq Patel, Paolo Ferroni
  Pages: 1 - 15
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-11T07:41:57Z
  DOI: 10.1080/00295450.2023.2197667
Evaluation of Control Rod Interaction Measurement in the Prototype Fast
Reactor Monju
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  Authors: Kazuya Ohgama, Taira Hazama, Hiroki Katagiri, Atsushi Takegoshi
  Pages: 1 - 18
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-11T07:35:56Z
  DOI: 10.1080/00295450.2023.2197660
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under
High-Pressure Flow Boiling Conditions in TRTL
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  Authors: Nicholas A. Meehan, Seok Bin Seo, Trevor K. Howard, Nicholas R. Brown
  Pages: 1 - 25
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-11T07:25:20Z
  DOI: 10.1080/00295450.2023.2195355
Evaluation of BORAL Panels from an Operating Spent Fuel Pool
Open Access Article
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  Authors: Hatice Akkurt
  Pages: 1 - 14
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-05-01T06:36:44Z
  DOI: 10.1080/00295450.2023.2196234
Reliability Evaluation of Complex Nuclear Energy Redundancy Systems with
Atypical Time-Distribution Events
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  Authors: Shaoxuan Wang, Zhixian Lin, Ming Sun, Yuantao Yao, Jie Wu, Daochuan Ge
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-04-27T11:12:36Z
  DOI: 10.1080/00295450.2023.2195357
A Monte Carlo Study for Soft Tissue Equivalency of Potential Polymeric
Biomaterials Used in Carbon Ion Radiation Therapy
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  Authors: Fatih Ekinci, Erkan Bostanci, Mehmet Serdar Güzel, Özlem Dagli
  Pages: 1 - 11
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-04-21T04:01:09Z
  DOI: 10.1080/00295450.2023.2188144
Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in
Gas-Cooled Fast Reactors
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  Authors: Londrea J. Garrett, Milos Burger, Adam Burak, Xiaodong Sun, Piyush Sabharwall, Igor Jovanovic
  Pages: 1 - 8
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-04-18T03:58:19Z
  DOI: 10.1080/00295450.2023.2196233
Design and Assessment of the New CIRCE-THETIS Facility for the Development
of Heavy Liquid Metal Cooled Fast Reactors
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  Authors: Pierdomenico Lorusso, Ivan Di Piazza, Daniele Martelli, Mariano Tarantino
  Pages: 1 - 22
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-04-17T04:24:38Z
  DOI: 10.1080/00295450.2023.2189903
2D(r,t) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel
Performance Code ALCYONE
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  Authors: J. Sercombe, V. D’Ambrosi, S. Béjaoui, I. Zacharie-Aubrun
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-04-17T04:12:40Z
  DOI: 10.1080/00295450.2023.2188138
High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for
Heat Pipe Microreactors
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  Authors: Carolina da Silva Bourdot Dutra, Elia Merzari, John Acierno, Adam Kraus, Annalisa Manera, Victor Petrov, Taehwan Ahn, Pei-Hsun Huang, Dillon Shaver
  Pages: 1 - 25
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-04-17T04:06:46Z
  DOI: 10.1080/00295450.2023.2181040
Criticality Evaluation During Fuel Debris Particle Sedimentation Using
Coupled DEM-MPS Code
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  Authors: Shigeki Shiba, Daiki Iwahashi, Tsuyoshi Okawa
  Pages: 1 - 10
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-04-13T06:51:59Z
  DOI: 10.1080/00295450.2023.2191588
Experimental Results of PbLi-Water Reaction Performed in LIFUS5/Mod3
Separate Effect Test Facility
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  Authors: Nicolò Badodi, Antonio Cammi, Marica Eboli, Daniele Martelli, Alessandro Del Nevo
  Pages: 1 - 15
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-04-13T06:42:08Z
  DOI: 10.1080/00295450.2023.2188984
Liquid-Metal Thermal-Hydraulic Numerical Analyses in Support of the
Upcoming CIRCE-THETIS Experimental Campaign
Open Access Article
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  Authors: Pietro Stefanini, Francesco Galleni, Ivan Di Piazza, Andrea Pucciarelli
  Pages: 1 - 15
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-27T07:42:17Z
  DOI: 10.1080/00295450.2023.2189892
Radioactive Aerosol Control and Decontamination in the Decommissioning of
the Fukushima Daiichi Nuclear Power Station
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  Authors: Avadhesh Kumar Sharma, Hui Liang, Ruicong Xu, Erdal Ozdemir, Shuichiro Miwa, Ryohei Terabayashi, Shunichi Suzuki, Marco Pellegrini, Shuichi Hasegawa, Nejdet Erkan
  Pages: 1 - 14
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-27T07:38:20Z
  DOI: 10.1080/00295450.2023.2186675
Experimental Analysis of Steam Generator Tube Rupture in CIRCE Facility
for MYRRHA Configuration
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  Authors: Alessio Pesetti, Mariano Tarantino
  Pages: 1 - 21
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-22T09:28:20Z
  DOI: 10.1080/00295450.2023.2185050
Heat Transfer Analysis of Core Melt Contact with a CANDU Calandria
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  Authors: Robert David
  Pages: 1 - 9
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-21T02:32:32Z
  DOI: 10.1080/00295450.2023.2188145
Data-Driven RANS Turbulence Closures for Forced Convection Flow in Reactor
Downcomer Geometry
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  Authors: Arsen S. Iskhakov, Cheng-Kai Tai, Igor A. Bolotnov, Tri Nguyen, Elia Merzari, Dillon R. Shaver, Nam T. Dinh
  Pages: 1 - 18
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-15T08:36:58Z
  DOI: 10.1080/00295450.2023.2185056
Modeling of the P2M Past Fuel Melting Experiments with the FEMAXI-8 Code
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  Authors: Afiqa Mohamad, Yutaka Udagawa
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-13T07:48:58Z
  DOI: 10.1080/00295450.2023.2185061
Thermal-Hydraulic Characterization and Numerical Modeling with RELAP5 Code
of ATHENA Secondary Loop
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  Authors: Tommaso Del Moro, Fabio Giannetti, Mariano Tarantino, Pierdomenico Lorusso, Marco Caramello, Damiano Vitale Di Maio, Marin Constantin
  Pages: 1 - 17
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-09T04:32:50Z
  DOI: 10.1080/00295450.2023.2183025
Evaluation of Sodium Radioactivity in the Primary System of the Prototype
Fast Reactor Monju
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  Authors: Tetsuya Mouri, Kazuya Ohgama, Taira Hazama
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-09T04:24:50Z
  DOI: 10.1080/00295450.2023.2181044
Oh, My Darling Clementine: A Detailed History and Data Repository of the
Los Alamos Plutonium Fast Reactor
Open Access Article
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  Authors: Hannah K. Patenaude, Franz J. Freibert
  Pages: 1 - 45
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-09T04:23:20Z
  DOI: 10.1080/00295450.2023.2176686
Coupling of CTF and RELAP5-3D Within an Enhanced Fidelity Nuclear Power
Plant Simulator
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  Authors: Aaron J. Wysocki, Robert K. Salko, Igor Arshavsky
  Pages: 1 - 19
  Abstract: .
  
  Citation: Nuclear Technology
  PubDate: 2023-03-09T04:16:58Z
  DOI: 10.1080/00295450.2023.2175596
Multiphase Turbulence Modeling Using Sparse Regression and Gene Expression
Programming
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  Authors: S. Beetham, J. Capecelatro
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  PubDate: 2023-03-07T04:16:11Z
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The Versatile Loop Facility: A New Infrastructure for Testing Components
and Systems of Lead Fast Reactor Technology
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Modeling of the P2M Past Fuel Melting Experiments with the Fuel
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A Hydrothermal Phase Diagram for the Low-Temperature Synthesis of
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Numerical Simulation of Wall Condensation from a Superheated Steam and Air
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Steady-State and Transient Compliance of CIRCE-THETIS CFD Model
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A Fan-Controlled Sodium-to-Air Heat Exchanger Configuration for Failsafe
Decay Heat Removal in Sodium-Cooled Fast Reactors
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Analysis and Preliminary Design of Primary Heat Exchanger Failure Testing
Facility for Lead-Cooled Fast Reactors
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Design and Suitability Analysis of FPGA-Based TCP/IP Offload Module for
Control Systems of FBRs
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Condition Assessment of Nuclear Power Plant Equipment Based on Machine
Learning Methods: A Review
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  Authors: Yong Xu, Yunze Cai, Lin Song
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  PubDate: 2023-02-27T08:46:11Z
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Treatment of Uranyl Nitrate Solution by Nanofiltration
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  PubDate: 2023-02-27T08:42:33Z
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Experiments on Slug Flow Dynamics in Helically Coiled Tubes
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  Authors: Yuichi Murai, Masaaki Ishikawa
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  PubDate: 2023-02-24T06:55:47Z
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Comprehensive Comparison of Nuclear Materials in BNPP Fuel Assemblies
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Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of
Steam Generator Tube Degradation Using Dynamic Event Tree Analysis
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  Authors: Jintae Kim, Asad Ullah Amin Shah, Hyun Gook Kang, Tunc Aldemir
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  PubDate: 2023-02-23T09:24:02Z
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Advanced Instrumentation and Modeling Framework for Two-Phase Flow
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  Authors: Mamoru Ishii, Yang Zhao, Guanyi Wang, Zhuoran Dang
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  PubDate: 2023-02-22T05:28:53Z
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Modeling of an Energy-Diverse Embedded Grid for Microreactor Integration
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Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power
Station Unit 3
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  Authors: Takuya Yamashita, Takeshi Honda, Masato Mizokami, Kenichiro Nozaki, Hiroyuki Suzuki, Marco Pellegrini, Takeshi Sakai, Ikken Sato, Shinya Mizokami
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RANS-Based CFD Simulation of Jet-Induced Mixing and Jet Impingement on
Large Bubble in Microgravity
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An Assessment of Heterogeneous Effects on System Reactivity for
Criticality Safety Analyses with LEU+ and HALEU Materials
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Uncertainty Quantification for Multiphase Computational Fluid Dynamics
Closure Relations with a Physics-Informed Bayesian Approach
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  PubDate: 2023-02-16T07:21:46Z
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Effects of Pipe Inclination on Global Two-Phase Flow Parameters
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  Authors: Drew Ryan, Ran Kong, David Kang, Adam Dix, Seungjin Kim, Jiawei Bian
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  PubDate: 2023-02-16T07:17:42Z
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Molybdenum-99 from Molten Salt Reactor as a Source of Technetium-99m for
Nuclear Medicine: Past, Current and Future of Molybdenum-99
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  Authors: Jisue Moon, Kristian Myhre, Hunter Andrews, Joanna McFarlane
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  PubDate: 2023-02-16T07:15:44Z
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Thermal-Hydraulic Analysis of Inward and Outward Fuel Plate Buckling in a
Typical MTR Reactor
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  PubDate: 2023-02-14T06:37:56Z
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Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes
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  PubDate: 2023-02-10T06:48:51Z
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Interphase and Intergroup Mass Transfer in the Two-Group Two-Fluid Model
in Flows with Phase Change
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  PubDate: 2023-02-09T04:07:24Z
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Experiment and Modeling of Interfacial Area Concentration of Liquid Film
in Upward Annular Two-Phase Flow
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  Authors: Guanyi Wang, Mamoru Ishii
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  PubDate: 2023-02-09T04:03:00Z
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Integral-Effect Test for Loss of Residual Heat Removal System During
Mid-Loop Operation in ATLAS Facility
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  Authors: J. B. Lee, B. U. Bae, Y. S. Park, J. Kim, S. Cho, N. H. Choi, K. H. Kang
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  PubDate: 2023-02-09T04:00:07Z
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Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop
with Flashing Instability
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  Authors: Taiyang Zhang, Caleb S. Brooks
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  Citation: Nuclear Technology
  PubDate: 2023-02-06T06:55:29Z
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Research to Develop Flood Barrier Testing Strategies for Nuclear Power
Plants
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  Authors: Zhegang Ma, Sai Zhang, Chad Pope, Curtis Smith
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  PubDate: 2023-01-26T09:01:28Z
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On the Language of Reliability: A System Engineer Perspective
Open Access Article
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  Authors: D. Mandelli, C. Wang, S. Hess
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  PubDate: 2023-01-23T05:23:07Z
  DOI: 10.1080/00295450.2022.2143210
Cross-Section Calculations for the Production of 123I and 124I
Radioisotopes via (p,n) and (p,2n) Reactions Using Collective Nuclear
Level Density Model
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  Authors: Deniz Canbula, Bora Canbula
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  PubDate: 2023-01-20T10:21:54Z
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High-Resolution X-Ray Radiography Methods Developed for Post-CHF
Experiment
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  Authors: Julio Diaz, Qingqing Liu, Victor Petrov, Annalisa Manera, Xiaodong Sun
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  Citation: Nuclear Technology
  PubDate: 2023-01-13T08:58:07Z
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Operation Cycle Length Extension of a Konvoi PWR — Requirements and
Experience from Operator’s Viewpoint
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  Authors: Kai Kosowski, Marcus Seidl
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  PubDate: 2023-01-11T04:14:05Z
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An Experimental and Theoretical Examination of Air Ingress Rates During
Small- and Medium-Break Air Ingress Accidents
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  Authors: Zachary Welker, Annalisa Manera, Victor Petrov, Paolo Balestra
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  Citation: Nuclear Technology
  PubDate: 2022-12-09T10:25:07Z
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Versatile Economic Risk Tool
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  Authors: J. Miller, S. Ercanbrack, C. L. Pope
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  Citation: Nuclear Technology
  PubDate: 2022-12-06T05:25:37Z
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On the Development of a Novel Acoustic Flowmeter for High-Temperature
Gas-Cooled Reactors
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  Authors: Jiaxin Mao, Victor Petrov, Annalisa Manera, Trevor K. Howard, Sacit M. Cetiner
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  Citation: Nuclear Technology
  PubDate: 2022-11-01T11:46:45Z
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Validation Matrix for Pool Scrubbing Models
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  Authors: L. E. Herranz, F. Sánchez, S. Gupta
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  Citation: Nuclear Technology
  PubDate: 2022-11-01T11:46:24Z
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Automatic Generation of Event Trees and Fault Trees: A Model-Based
Approach
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  Authors: Diego Mandelli, Andrea Alfonsi, Tunc Aldemir
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  Citation: Nuclear Technology
  PubDate: 2022-09-14T08:02:58Z
  DOI: 10.1080/00295450.2022.2105780