Nuclear Engineering and Technology最新文献_第9页

Optimizing spent nuclear fuel cask loading for VVER-440 fuel 优化 VVER-440 燃料乏核燃料桶的装载

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-05 DOI: 10.1016/j.net.2024.07.014

M. Lovecký, J. Závorka

引用次数: 0

Hydrodynamics coupled circulating-fuel reactor equations in comoving frame and their analytical solutions for molten salt reactors 移动框架下的水动力学耦合循环燃料反应堆方程及其对熔盐反应堆的解析解

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-04 DOI: 10.1016/j.net.2024.07.008

Ayhan Yılmazer, Gökhan Pediz

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Continuous mapping of nuclear reactor core power using artificial neural network even in the presence of inactive detectors 利用人工神经网络持续绘制核反应堆堆芯功率图，即使在探测器处于非活动状态的情况下也是如此

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-04 DOI: 10.1016/j.net.2024.07.007

João D. Talon, Aquilino S. Martinez, Alessandro C. Gonçalves

{"title":"Continuous mapping of nuclear reactor core power using artificial neural network even in the presence of inactive detectors","authors":"João D. Talon, Aquilino S. Martinez, Alessandro C. Gonçalves","doi":"10.1016/j.net.2024.07.007","DOIUrl":"https://doi.org/10.1016/j.net.2024.07.007","url":null,"abstract":"Monitoring the radial power distribution during the operation of a pressurized light water reactor (PWR) is crucial for ensuring safe operating conditions and achieving high levels of fuel burnup. This paper introduces a methodology utilizing Artificial Neural Networks (ANN) for reconstructing the radial power distribution in the core of a Pressurized Water Reactor (PWR) with a hot full power of 1876 MWth, such as the Angra 1 reactor. This approach uses measurements from Self-Powered Neutron Detectors (SPND), simulated through the SERPENT code. The use of ANN demonstrated good accuracy in predicting the radial power distribution with an average relative error of 1.27%, considering 36 active detectors, with maximum relative error of 6.99%. Moreover, the proposed process demonstrated robust performance, even when measurements from one, two, or three SPND detectors were unavailable, resulting in errors of 1.24%, 1.13 %, and 1.09%, respectively. Therefore, the methodology ensures a reliable reconstruction of the radial power distribution, even when SPND detector measurements are unavailable, enabling the optimization of detector use and contributing to the increase of operational safety margins.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141612798","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}

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Analysis of the atomic ratio of H and Zr effect on the neutronics parameters of ZrH moderated space nuclear reactor 分析 H 和 Zr 原子比对 ZrH 慢化空间核反应堆中子参数的影响

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-04 DOI: 10.1016/j.net.2024.07.009

Xiaoliang Zou, Yanting Sun, Bo Yang, Yibao Liu

{"title":"Analysis of the atomic ratio of H and Zr effect on the neutronics parameters of ZrH moderated space nuclear reactor","authors":"Xiaoliang Zou, Yanting Sun, Bo Yang, Yibao Liu","doi":"10.1016/j.net.2024.07.009","DOIUrl":"https://doi.org/10.1016/j.net.2024.07.009","url":null,"abstract":"Zirconium hydride (ZrH) is an ideal moderator for space nuclear reactors due to its exceptional properties, including high hydrogen content, small neutron absorption cross section, and high operating temperature. The primary goal of this study is to examine how the atomic ratio of H to Zr (H/Zr ratio) influences the neutronics parameters of a ZrH moderated space nuclear reactor, with a focus on establishing a reliable reference for ensuring the optimal safety and minimization of such reactors. The neutronics calculation based on the ZrH moderated space nuclear reactor named Topaz-II is performed using the Reactor Monte Carlo code (RMC code) with the ENDF/VII cross-section database. The effects of the H/Zr ratio were studied with a particular focus on the initial k, the burnup, the temperature reactivity coefficient and the criticality safety. The results show that with the increase of the H/Zr ratio, the initial k increases while the drums’ worth decreases. The Moderator Temperature Coefficient (MTC) is a positive value that rises as the H/Zr ratio increases. In the dropping accidents, the reactor full of voids with seawater is more serious, and the introduced reactivity decreases with the increase of the H/Zr ratio.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141612795","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

Preparation and radiation shielding features of high density, transparent borosilicate glasses with different Bi2O3 contents 不同 Bi2O3 含量的高密度透明硼硅玻璃的制备和辐射屏蔽特性

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-04 DOI: 10.1016/j.net.2024.07.013

M.I. Sayyed, M. Rashad, Chaitali V. More, Anjan Kumar

引用次数: 0

Radiation effects on multi-channel Forksheet-FET and Nanosheet-FET considering the bottom dielectric isolation scheme 考虑底部电介质隔离方案的多通道叉片场效应晶体管和纳米片场效应晶体管的辐射效应

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-03 DOI: 10.1016/j.net.2024.06.031

Gunhee Choi, Jongwook Jeon

{"title":"Radiation effects on multi-channel Forksheet-FET and Nanosheet-FET considering the bottom dielectric isolation scheme","authors":"Gunhee Choi, Jongwook Jeon","doi":"10.1016/j.net.2024.06.031","DOIUrl":"10.1016/j.net.2024.06.031","url":null,"abstract":"<div><div>This study analyzes the single-event transient (SET) characteristics of alpha particles on multi-channel Forksheet-FET and Nanosheet-FET at the device and circuit levels through 3D TCAD simulations. The study investigates the differences in SET responses based on the energy and incident position of incoming alpha particles, considering the structural variances between Forksheet-FET and Nanosheet-FET, as well as the presence or absence of bottom dielectric isolation (BDI) in the fabrication process. Specifically, the introduction of BDI is observed to significantly suppress the voltage drop caused by ‘unintended' current, as it can block the substantial electron-hole pairs (EHP) generated by injected alpha particles in the bulk substrate from reaching the FET terminals. Furthermore, it was confirmed that the size of abnormal current decreases as the energy of the injected alpha particle increases. Additionally, evaluating the response to SET based on the fundamental logic circuit, the CMOS inverter, revealed relatively small abnormal voltage drops for both Forksheet and Nanosheet when BDI was applied, confirming high immunity to radiation effects. Moreover, it can be observed that the application of BDI enhances reliability from a memory perspective by effectively suppressing voltage flips in the SRAM's cross-coupled latch circuit.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.6,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141612806","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

Confirmation bias, information selection, and belief reinforcement about the safety/risk of nuclear spent fuel storage facilities 关于核乏燃料贮存设施安全/风险的确认偏差、信息选择和信念强化

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-03 DOI: 10.1016/j.net.2024.07.006

Daeyoun Lee, Woo J. Kim, Young Rok Choi

{"title":"Confirmation bias, information selection, and belief reinforcement about the safety/risk of nuclear spent fuel storage facilities","authors":"Daeyoun Lee, Woo J. Kim, Young Rok Choi","doi":"10.1016/j.net.2024.07.006","DOIUrl":"https://doi.org/10.1016/j.net.2024.07.006","url":null,"abstract":"This study investigates the phenomenon of confirmation bias in information selection in the context of nuclear spent fuel (NSF) storage facilities. An online survey was administered to a sample of 321 residents in South Korea. They were asked to assess their beliefs about the safety/risk of NSF storage facilities before and after their exposure to additional information. Our findings show a positive association between the initial belief and confirmation bias, suggesting that the research participants tend to select articles consistent with their beliefs about the safety/risk of the facility. Trust in government is negatively related to confirmation bias, implying that residents with a greater level of trust in government are more likely to choose information opposing their initial beliefs. Finally, this study finds the self-reinforcing and potentially polarizing nature of individuals' beliefs about the safety/risk of NSF storage facilities as residents’ initial beliefs are reinforced rather than challenged after they reviewed self-selected articles. Implications for public policy and communication strategies related to improving the acceptance of NSF storage facilities are discussed.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141612810","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

Assessing the impact of DIONISIO-SubChanFlow code coupling in nuclear fuel performance simulations 评估核燃料性能模拟中 DIONISIO-SubChanFlow 代码耦合的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-03 DOI: 10.1016/j.net.2024.06.048

Mauricio Exequiel Cazado , Victor Hugo Sánchez-Espinoza , Alejandro Soba

{"title":"Assessing the impact of DIONISIO-SubChanFlow code coupling in nuclear fuel performance simulations","authors":"Mauricio Exequiel Cazado , Victor Hugo Sánchez-Espinoza , Alejandro Soba","doi":"10.1016/j.net.2024.06.048","DOIUrl":"10.1016/j.net.2024.06.048","url":null,"abstract":"<div><div>Realistic simulation of nuclear fuel performance requires not only validated models capable of describing the thermomechanical phenomena that take place within the fuel under irradiation conditions, but a detailed description of the thermal hydraulics of the channel surrounding the fuel rods, which provides the boundary conditions of the system. In this work, the main results and outlooks of coupling the thermal hydraulics code SubChanFlow with the fuel performance code DIONISIO are presented. To achieve this, an internal coupling was implemented, wherein DIONISIO is used as a master code controlling SubChanFlow as a thermal hydraulics subroutine replacing the simplified version already embedded in DIONISIO. Several tests were conducted to ensure the performance and quality of the coupling under normal operation conditions as a first approach. In addition, it was observed that the coupling demonstrated a significant improvement in the description of the cladding temperature and related variables, such as oxide thickness and hydrogen uptake, when compared with experimental data.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.6,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141612800","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

Neutron attenuation performance of EPDM rubber with BN Nanoparticles/B2O3 composite and studying physical, thermal and mechanical properties 三元乙丙橡胶与 BN 纳米粒子/B2O3 复合材料的中子衰减性能以及物理、热和机械性能研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-02 DOI: 10.1016/j.net.2024.06.019

H.M. Eyssa , Nabila A. Maziad , Wagdy Kansouh , Wageeh Ramadan

{"title":"Neutron attenuation performance of EPDM rubber with BN Nanoparticles/B2O3 composite and studying physical, thermal and mechanical properties","authors":"H.M. Eyssa , Nabila A. Maziad , Wagdy Kansouh , Wageeh Ramadan","doi":"10.1016/j.net.2024.06.019","DOIUrl":"10.1016/j.net.2024.06.019","url":null,"abstract":"<div><div>The current study has focused on evolving materials with high attenuation performance and vigorous mechanical properties. Nano hexagonal boron nitride (h-BN) has been synthesized from boric acid and urea and then heated at a low temperature. XRD, SEM, EDX-mapping images, and FTIR investigated the nano h-BN synthesized and boron oxide (B2O3) milled. The new nanocomposites based on ethylene propylene diene rubber (EPDM), different concentrations of h-BN NPs, and B<sub>2</sub>O<sub>3</sub> have been prepared. The physical, mechanical, and thermal properties and neutron attenuation behavior of nanocomposites were characterized. The shielding properties were determined by measuring the fast neutrons and total gamma-ray attenuation coefficients of the <sup>239</sup>Pu-α-<sup>9</sup>Be neutron source. It was seen that adding a coupling agent (maleic anhydride) was appropriate for improving interfacial adhesions between EPDM chains and the nanofiller h-BN and B<sub>2</sub>O<sub>3</sub> compared to EPDM unloaded. From the results, we observe that EPDM loaded with nano h-BN and nano h-BN/B<sub>2</sub>O<sub>3</sub> was noticeably boosted over that of the unloaded EPDM for tensile strength (TS), EPDM/nano h-BN/B<sub>2</sub>O<sub>3</sub> had a high TS at a concentration of 3 % h-BN/10 % B<sub>2</sub>O<sub>3</sub> (42 %) compared with unloaded EPDM. Moreover, EPDM/3 % h-BN and EPDM/3 % h-BN/10 % B<sub>2</sub>O<sub>3</sub> had the highest thermal stability until 490 °C compared to unloaded EPDM is stable at 350 °C. Finally, the maximum macroscopic effective shielding behaviors and removal cross-section are estimated by incorporating h-BN 3 % into EPDM.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.6,"publicationDate":"2024-07-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141698021","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

Systematic analysis for the thermal stability assessment of 166Ho production using HANARO: An in silico study 利用 HANARO 对 166Ho 生产的热稳定性评估进行系统分析：一项硅学研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-02 DOI: 10.1016/j.net.2024.07.001

Taeyun Kim , Bo-Young Han , Seongwoo Yang , Jaegi Lee , Gwang-Min Sun , Byung-Gun Park , Sung-Joon Ye

{"title":"Systematic analysis for the thermal stability assessment of 166Ho production using HANARO: An in silico study","authors":"Taeyun Kim , Bo-Young Han , Seongwoo Yang , Jaegi Lee , Gwang-Min Sun , Byung-Gun Park , Sung-Joon Ye","doi":"10.1016/j.net.2024.07.001","DOIUrl":"10.1016/j.net.2024.07.001","url":null,"abstract":"<div><div>Medical radioisotopes (RIs) are widely used in the diagnosis and treatment of tumors. Theranostic RIs, such as <sup>131</sup>I, <sup>166</sup>Ho, <sup>177</sup>Lu, and <sup>186</sup>Re, are particularly notable for their ability to enable diagnosis and treatment simultaneously. Conducting irradiation tests using the High-flux Advanced Neutron Application Reactor (HANARO), a 30-MW multipurpose research reactor, enables the production of these medical RIs. Prior to irradiation tests, it is crucial to assess whether they affect the thermal stability of irradiated materials and the thermal-hydraulic safety of HANARO. This study systematically investigates the feasibility of <sup>166</sup>Ho production using the isotope production irradiation hole of HANARO, focusing on thermal stability. The nuclear heating rates of the RI production target and RI capsule are calculated using MCNP6, and the calculated nuclear heating rates are used for three-dimensional heat transfer analysis using COMSOL Multiphysics. Under the assumed conditions in this study, <sup>166</sup>Ho production did not compromise the thermal stability of the RI production target and RI capsule; consequently, the thermal-hydraulic safety criteria of HANARO could be satisfied. This study can serve as a valuable reference for evaluating the thermal stability of irradiated materials and the thermal-hydraulic safety of HANARO, which must be performed before irradiation tests using HANARO.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.6,"publicationDate":"2024-07-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141612803","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