Nuclear Engineering and Technology最新文献_第10页

Effect of bi-directional ground motions on the seismic pounding of adjacent NPP structures

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-21 DOI: 10.1016/j.net.2025.103542

Bidhek Thusa , Duy-Duan Nguyen , Md Samdani Azad , Tae-Hyung Lee

{"title":"Effect of bi-directional ground motions on the seismic pounding of adjacent NPP structures","authors":"Bidhek Thusa , Duy-Duan Nguyen , Md Samdani Azad , Tae-Hyung Lee","doi":"10.1016/j.net.2025.103542","DOIUrl":"10.1016/j.net.2025.103542","url":null,"abstract":"<div><div>This study aims to investigate the structural pounding of two adjacent RCB and AB under bi-directional ground motions. Furthermore, this study also investigates the influence of strong bi-directional ground motions on the seismic response interaction of adjacent RCB and AB. Finite element models (FEM) for both RCB and AB are constructed in SAP2000 using multi-layer shell model (MLSM) with a design level separation (i.e., seismic gap). Two sets of ground motions are utilized to perform time history analyses of the combined RCB and AB, in which each set of motions comprising 10 bi-directional design-based earthquakes (DBEs), and 10 strong bi-directional ground motions ever recorded respectively. Seismic displacement is monitored at the two most susceptible locations of AB and RCB. The observation shows that RCB is prone to experience damage due to seismic impact of adjacent AB under very strong bi-directional ground motions. Additionally, it is noticed that the probability of the occurrence of seismic pounding between adjacent RCB and AB increases significantly when the PGA of strong bi-directional motion is higher than 1.5g. These results emphasize that the current design separation of 5.08 cm gap between adjacent RCB and AB may not be sufficient to prevent seismic impact during strong earthquakes.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103542"},"PeriodicalIF":2.6,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682208","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Characterization of real-time dose measurement using monitor ionization chamber in electron beam FLASH radiotherapy

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-19 DOI: 10.1016/j.net.2025.103551

Xinle Lang , Faming Luo , Min Li , Kai Zhou , Juan Li , Zhenguo Hu , Ruishi Mao , Zhiguo Xu , Guoqing Xiao

{"title":"Characterization of real-time dose measurement using monitor ionization chamber in electron beam FLASH radiotherapy","authors":"Xinle Lang , Faming Luo , Min Li , Kai Zhou , Juan Li , Zhenguo Hu , Ruishi Mao , Zhiguo Xu , Guoqing Xiao","doi":"10.1016/j.net.2025.103551","DOIUrl":"10.1016/j.net.2025.103551","url":null,"abstract":"<div><div>FLASH radiotherapy (RT) reduces the level of irradiation damage to normal tissue by utilizing an ultra-high dose rate to deliver the dose into the tumor target area in millisecond-order time. The ultra-high dose rate <strong><em>(≥</em>40 Gy/s<em>)</em></strong> renders existing online dose monitors largely ineffective or dose-rate dependent. In this study, the dose distribution based on a 9 MeV ultra-high dose rate electron beam FLASH irradiation platform was investigated using Gafchromic EBT3 film, and its flatness deviation within ±5 % and symmetry deviation within ±3 % meets the standard requirements. <strong><em>We also explored the saturation effect observed in ionization chambers (IC) used for online monitoring by reducing the sensitive volume of the chamber and its air pressure.</em></strong> Real-time dose monitoring was successfully achieved with the electron beam at a source skin distance (SSD) of 100 cm and a dose rate of 250 Gy/s, demonstrating a linearity deviation within ±2 %. The <strong><em>IC</em></strong> correction factor was calculated according to the IAEA TRS-398 standard. In conclusion, this study successfully established quality assurance for electron beam irradiation at ultra-high dose rates using Gafchromic EBT3 film and enabled effective online dose monitoring. This work provides a dosimetric foundation for future scientific research and clinical applications of FLASH RT.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 6","pages":"Article 103551"},"PeriodicalIF":2.6,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143679437","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

RBE evaluation during the vertebral and brain cancer treatment using low-kV X-rays: A hybrid simulation approach

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-19 DOI: 10.1016/j.net.2025.103552

Reza Shamsabadi, Hamid Reza Baghani, Zeynab Alvarmir

{"title":"RBE evaluation during the vertebral and brain cancer treatment using low-kV X-rays: A hybrid simulation approach","authors":"Reza Shamsabadi, Hamid Reza Baghani, Zeynab Alvarmir","doi":"10.1016/j.net.2025.103552","DOIUrl":"10.1016/j.net.2025.103552","url":null,"abstract":"<div><div>Intraoperative radiotherapy (IORT) using INTRABEAM machine and specific needle applicator is a candidate modality for vertebral and brain cancer treatment. Current study aims to evaluate the relative biologic effectiveness (RBE) values of low energy X-rays emitted from the surface of needle applicator during the IORT of vertebral and brain tumors, through a hybrid Monte Carlo (MC) simulation approach.</div><div>To estimate RBE values, Geant4 was employed to simulate the INTRABEAM X-ray source along with needle applicator as well as scoring released secondary electron spectra within considered tissues. Then, RBE values were estimated by Monte Carlo damage simulation (MCDS) code.</div><div>An increasing trend of RBE<sub>DSB</sub> (RBE for DNA double strand breaks) values was found by increasing the distance from applicator surface. The maximum RBE<sub>DSB</sub> values were obtained for vertebral bone (C4) among the investigated tissues due to higher physical density and Z<sub>eff</sub> values. Cell oxygenation level also affected RBE<sub>DSB</sub> with a maximum value of 64 % when moving from 0.3 % to 4 % level.</div><div>From the results, it can be concluded that RBE values during the low energy X-ray IORT of brain and vertebral column tumors using dedicated needle applicator can be affected by considerable differences in tissue composition and cell oxygenation level.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103552"},"PeriodicalIF":2.6,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682565","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Advanced fuel performance analysis of multi-layered coated accident-tolerant fuel (ATF) cladding using a coupled multiphysics approach

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-19 DOI: 10.1016/j.net.2025.103549

Jiwon Mun , Saeed A. Alameri , Ho Jin Ryu

{"title":"Advanced fuel performance analysis of multi-layered coated accident-tolerant fuel (ATF) cladding using a coupled multiphysics approach","authors":"Jiwon Mun , Saeed A. Alameri , Ho Jin Ryu","doi":"10.1016/j.net.2025.103549","DOIUrl":"10.1016/j.net.2025.103549","url":null,"abstract":"<div><div>This study aims to develop the KAFKA code, built on the ABAQUS™ framework, to conduct detailed simulations of Accident Tolerant Fuel (ATF) cladding coated on both the inner and outer surfaces, in order to evaluate the thermal and mechanical performance of coated cladding under different operational conditions. The KAFKA code allows for advanced simulations of fuel rod behaviors, accounting for temperature- and burnup-dependent material properties, fuel swelling, densification, fission gas release, as well as the mechanical responses of cladding and coatings. The results from fully coupled multiphysics modeling demonstrated that Cr and FeCrAl coatings delayed gap closure and reduced hoop stress on the Zr-4 substrate, mitigating failure mechanisms like fatigue, stress corrosion cracking, and creep rupture under steady-state and daily load-following conditions. These findings indicate that the use of coupled multiphysics code enables a more precise evaluation of coated ATF cladding and nuclear fuel performance, contributing to the safer operation of nuclear reactors.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103549"},"PeriodicalIF":2.6,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682142","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Crack shape idealization of a complex crack to an equivalent through-wall crack using net-section collapse

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-19 DOI: 10.1016/j.net.2025.103544

Ju-Won Choi, Jun-Geun Park, Nam-Su Huh

{"title":"Crack shape idealization of a complex crack to an equivalent through-wall crack using net-section collapse","authors":"Ju-Won Choi, Jun-Geun Park, Nam-Su Huh","doi":"10.1016/j.net.2025.103544","DOIUrl":"10.1016/j.net.2025.103544","url":null,"abstract":"<div><div>This paper proposes a crack shape idealization method based on the net-section collapse concept to predict the fracture behavior of pipes with complex cracks. The proposed method assumes that an idealized through-wall cracked pipe has an identical limit load to a pipe with a complex crack, given the same outer diameter and through-wall crack angle. By applying this approach, complex cracks can be idealized into simpler through-wall cracks. The comparison of limit loads between the idealized through-wall cracked pipe and the complex cracked pipe demonstrates good agreement. For experimental validation, the method was used to predict the maximum load of pipes with complex cracks, and the results were compared with actual pipe test data. Using the crack driving force diagram method, the predicted maximum load showed variations of 1 %–32 % compared to experimental results. Despite these variations, the proposed method provides a practical and reliable approach for predicting the maximum load of complex cracked pipes in both fully plastic and elastic-plastic regions, simplifying analysis while maintaining accuracy.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103544"},"PeriodicalIF":2.6,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143839579","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Numerical study of thermal-hydraulic behavior on the integral test facility of HPR1000 containment based on CONTHAC-3D

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-18 DOI: 10.1016/j.net.2025.103548

Ji Xing , Yuan Chang , Hui Wang , Gong-Lin Li , Ming Ding

{"title":"Numerical study of thermal-hydraulic behavior on the integral test facility of HPR1000 containment based on CONTHAC-3D","authors":"Ji Xing , Yuan Chang , Hui Wang , Gong-Lin Li , Ming Ding","doi":"10.1016/j.net.2025.103548","DOIUrl":"10.1016/j.net.2025.103548","url":null,"abstract":"<div><div>The integral test facility-platform for the integral thermal-hydraulic behavior of containment (PANGU), is used to study the thermal-hydraulic behavior of the containment under the action of the passive containment heat removal system (PCS) when accident occurs. An in-house code called CONTHAC-3D was developed to investigate the fundamental thermal-hydraulic phenomena occurring in the containment during accidents for nuclear power plants, and it also had the ability to simulate specific systems such as the PCS system, containment hydrogen control system, etc. In order to validate the capability of CONTHAC-3D code to simulate PCS system, the numerical model of the PANGU facility was established and three typical experimental scenarios were used to verify its ability. The results show that for the selected three accident scenarios, the PCS power calculated by CONTHAC-3D is slightly lower than the experimental data. However, in general, both the peak and long-term values of the containment atmospheric pressure, temperature and PCS heat removal power are kept within a small error range compared with experimental data. Therefore, it can be concluded that the PCS module developed in the CONTHAC-3D code can effectively track the power changes and flow fluctuations of the PCS system, and the thermal-hydraulic conditions in the facility.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103548"},"PeriodicalIF":2.6,"publicationDate":"2025-02-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681683","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Effects of vacancies on the behavior of H in ZrC: A first-principles study

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-17 DOI: 10.1016/j.net.2025.103550

Xun Lan , Jiajun Zhao , Dan Sun , Yong Xin , Zhipeng Sun , Xi Qiu , ShiChao Liu , Yuanming Li , Jijun Zhao

{"title":"Effects of vacancies on the behavior of H in ZrC: A first-principles study","authors":"Xun Lan , Jiajun Zhao , Dan Sun , Yong Xin , Zhipeng Sun , Xi Qiu , ShiChao Liu , Yuanming Li , Jijun Zhao","doi":"10.1016/j.net.2025.103550","DOIUrl":"10.1016/j.net.2025.103550","url":null,"abstract":"<div><div>Understanding the response of ZrC to irradiation damage is crucial for the successful implementation of ZrC materials in the new generation of nuclear reactors. In this study, we systematically investigate the behavior of single H atom, small H<sub><em>n</em></sub> clusters (<em>n</em> = 2–4), vacancies, and H-vacancy complexes in ZrC host lattice using first-principles calculations. Energetically, we find that H at the tetrahedral site surrounded by one C atom and three Zr atoms (I<sub>H<em>b</em></sub>) is more favorable than at the cube center site (I<sub>H<em>a</em></sub>). H<sub>C</sub> in ZrC exhibits the highest stability, followed by I<sub>H<em>b</em></sub>, I<sub>H<em>a</em></sub>, H<sub>Zr</sub>. The average formation energy of per H in H<sub>n</sub> cluster increases with the number of H atoms and two interstitial H atoms tend to exclude each other. Additionally, the average formation energy per H of H<sub><em>n</em></sub> clusters inside ZrC supercell with vacancies is lower than that inside perfect ZrC supercell. Combined the binding energy, the vacancies will promote the aggregation of H atoms. V<sub>Zr</sub> exhibits a greater capacity for hydrogen accommodation in comparison to V<sub>C</sub>, attributed to its larger vacant sites. The generally decreasing binding energy between H and H-vacancy complexes suggests that the attraction weakens and can even turn into repulsion as the number of H atoms increases.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103550"},"PeriodicalIF":2.6,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682063","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Cyclic behaviors of diffusion welded alloy 800H

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-16 DOI: 10.1016/j.net.2025.103536

Jong-Bae Hwang , Eung-Seon Kim

{"title":"Cyclic behaviors of diffusion welded alloy 800H","authors":"Jong-Bae Hwang , Eung-Seon Kim","doi":"10.1016/j.net.2025.103536","DOIUrl":"10.1016/j.net.2025.103536","url":null,"abstract":"<div><div>Diffusion welding creates monolithic joints with complex interiors, such as in the printed circuit heat exchanger (PCHE) for high-temperature reactors. PCHEs are mainly subjected to low cycle fatigue, which is caused by thermal contraction and expansion during the start-up/shutdown. To utilize PCHEs in high-temperature reactors, it is essential to understand the cyclic behaviors of the diffusion weldment (DFW). In this study fatigue tests were conducted on Alloy 800H in its as-received (AR) state with the diffusion weldment at 650 °C and 760 °C and a total strain range of 0.5–1.2 %. The heat absorbed during the diffusion welding process softened the DFW, allowing it to accommodate large plastic strains. Fatigue tests revealed that the fatigue life of the DFW was longer than that of the AR where the plastic strain dominates the fatigue life. However, the fatigue life of the DFW was shorter than that of the AR where the materials resisted the cyclic behavior based on their strengths. The location of crack initiation was outside the diffusion welding interface, indicating that the cyclic behaviors of the diffusion weldment depend on the thermal history of the manufacturing process.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103536"},"PeriodicalIF":2.6,"publicationDate":"2025-02-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682169","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A simulation approach for start-up without secondary neutron sources of Hualong One: A Monte-Carlo-deterministic framework

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-16 DOI: 10.1016/j.net.2025.103546

Jiandi Guo , Zhouyu Liu , Qingming He , Danbin Huang , Liangzhi Cao , Hongchun Wu

{"title":"A simulation approach for start-up without secondary neutron sources of Hualong One: A Monte-Carlo-deterministic framework","authors":"Jiandi Guo , Zhouyu Liu , Qingming He , Danbin Huang , Liangzhi Cao , Hongchun Wu","doi":"10.1016/j.net.2025.103546","DOIUrl":"10.1016/j.net.2025.103546","url":null,"abstract":"<div><div>Since secondary neutron sources in Pressurized Water Reactors (PWRs) continuously produce tritium, the technology of replacing these sources with spent fuel assemblies has been proposed to reduce such emissions. To this end, this study introduces a Monte-Carlo-Deterministic coupling simulation approach for the Hualong One start-up without secondary neutron sources, utilizing NECP-MCX and Bamboo-C. Firstly, the Monte Carlo model was refined by criticality calculation and the thermal neutron sensitivity coefficient of the detectors was then calibrated. The approach was subsequently validated through analysis of the calibration experiments utilizing secondary neutron sources during Cycle 2 fuel loading process. Finally, the count rate of ex-core source-range detectors with spent fuel assembly neutron sources was predicted. The results indicate that the maximum relative error of the source-range detector count rate during the Cycle 2 calibration experiments is 11.11 %. The results further predict that placing a spent fuel assembly with a burnup of 29.39 GWd/tU at position R06 or R08 within the reactor core will satisfy the requirements for the Hualong One start-up. In summary, the simulation approach presented in this paper provides theoretical support for the Hualong One start-up in the absence of secondary neutron sources and contributes to reducing tritium emissions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103546"},"PeriodicalIF":2.6,"publicationDate":"2025-02-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681686","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Decision tree based parameter identification and state estimation: Application to Reactor Operation Digital Twin

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-14 DOI: 10.1016/j.net.2025.103527

Rong Zhao , Lizhan Hong , Hongjun Ji , Qinyi Zhang , Shiquan Zhang , Qing Li , Helin Gong

{"title":"Decision tree based parameter identification and state estimation: Application to Reactor Operation Digital Twin","authors":"Rong Zhao , Lizhan Hong , Hongjun Ji , Qinyi Zhang , Shiquan Zhang , Qing Li , Helin Gong","doi":"10.1016/j.net.2025.103527","DOIUrl":"10.1016/j.net.2025.103527","url":null,"abstract":"<div><div>This study presents a comprehensive investigation into enhancing the performance of decision tree algorithms within the Reactor Operational Digital Twin (RODT) framework. Our previous work established the RODT and optimized the K-Nearest Neighbors (KNN) algorithm for its operation. Building on this foundation, we systematically explored decision tree techniques for both forward and inverse problems of the RODT. Through extensive experimentation, we integrated advanced techniques such as Bayesian optimization, GPU acceleration, and parallel processing to enhance the decision tree’s training efficiency and reduce its memory footprint. Our findings reveal that Gradient Boosting Decision Trees (GBDT) outperform KNN in accuracy for forward problems, while Adaboost, though slightly less accurate, offers comparable stability with respect to noisy measurements for inverse problems. Despite a slight dip in performance under noisy conditions, decision trees still hold promise in digital twin modeling. This research not only bridges the application gap of decision tree algorithms in digital twin modeling but also significantly improves the overall performance of the RODT. The insights from our experiments, particularly the synergy between GBDT and Bayesian optimization, offer valuable contributions to a broad spectrum of applications.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103527"},"PeriodicalIF":2.6,"publicationDate":"2025-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681747","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0