Nuclear Engineering and Technology最新文献_第6页

A new protective glass material against gamma ray: Thorough analysis to determine the impact of adding gadolinium (III) oxide 一种新型伽马射线防护玻璃材料：彻底分析确定添加氧化钆（III）的影响

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-08 DOI: 10.1016/j.net.2024.08.015

M.I. Sayyed, K.A. Mahmoud, Taha A. Hanafy

{"title":"A new protective glass material against gamma ray: Thorough analysis to determine the impact of adding gadolinium (III) oxide","authors":"M.I. Sayyed, K.A. Mahmoud, Taha A. Hanafy","doi":"10.1016/j.net.2024.08.015","DOIUrl":"https://doi.org/10.1016/j.net.2024.08.015","url":null,"abstract":"This work presents a study of the effect of replacing lead dioxide and gadolinium (III) oxide with boron trioxide on the physical, mechanical, and radiation shielding properties for the BO-NaO-ZnO-PbO-GdO glass systems. The Archimedes method confirms that the increase in the PbO+GdO concentration within the fabricated glass system in the range from 16 to 22 mol.% increases the fabricated glass samples' density from 4.052 to 4.408 g/cm. Additionally, the Makishima-Mackenzie model was utilized to investigate the influence of PbO+GdO on the mechanical properties of the investigated glass samples. The increase in the substituting of PbO+GdO decreases the fabricated glass samples' mechanical properties and micro-hardness. Furthermore, the Monte Carlo simulation method was applied for the estimation of the impact of PbO+GdO concentration on the fabricated samples' radiation shielding parameters. The increase in the concentration of PbO+GdO with range of (16, 18, 20 and 22) leads to increase the linear attenuation coefficient (LAC) to 8.014–11.517 cm at 0.06 MeV, 0.381–0.423 cm at 0.6 MeV, 0.133–0.149 cm at 5 MeV, and 0.132–0.154 cm at 15 MeV with the same order, respectively. Therefore, the introduction of PbO+GdO concentration enhances the fabricated glass samples' radiation shielding properties to be suitable for γ-ray shielding applications.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207266","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

Exploring helium retention from technical materials: Development and investigation 探索技术材料中的氦保留：开发与研究

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-06 DOI: 10.1016/j.net.2024.08.005

Andrew K. Gillespie, Cuikun Lin, Django Jones, Sandeep Puri, R.V. Duncan

{"title":"Exploring helium retention from technical materials: Development and investigation","authors":"Andrew K. Gillespie, Cuikun Lin, Django Jones, Sandeep Puri, R.V. Duncan","doi":"10.1016/j.net.2024.08.005","DOIUrl":"https://doi.org/10.1016/j.net.2024.08.005","url":null,"abstract":"Materials used to study nuclear fusion can retain atmospheric helium unless pretreated before an experiment. Understanding helium outgassing is important for accurate diagnostics in experiments surrounding nuclear fusion. The presence of helium is often cited as the primary evidence that a nuclear reaction has occurred, so it is imperative that known sources of helium are mitigated prior to proceeding with novel nuclear experiments. It is also necessary to ensure hermeticity when transferring gas aliquots from an experiment to a mass spectrometer. In this article, we present studies of helium leak rates in systems used in novel nuclear experiments. We also present studies of helium retention in materials subjected to various heating profiles and atmospheric concentrations. Without pretreatment, 12-inch lengths of both 3/8” diameter tubes and 1/2″ diameter stainless-steel 316 tubing yielded an average areal outgassing amount of 0.64 pmol/cm. If pretreatment is impractical, then the results may be scaled based on the tubing length necessary for constructing custom experimental equipment. It also may reabsorb He from the atmosphere in time. These studies also demonstrate that it is necessary to pretreat most materials prior to performing experiments where the presence of He is being used as an indicator for novel nuclear reactions.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207269","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

A step towards a sustainable environment in top-10 nuclear energy consumer countries: The role of financial globalization and nuclear energy 十大核能消费国向可持续环境迈出的一步：金融全球化和核能的作用

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-06 DOI: 10.1016/j.net.2024.08.011

Mumtaz Ali, Ahmed Samour, Suhaib Ahmed Soomro, Waqar Khalid, Turgut Tursoy

{"title":"A step towards a sustainable environment in top-10 nuclear energy consumer countries: The role of financial globalization and nuclear energy","authors":"Mumtaz Ali, Ahmed Samour, Suhaib Ahmed Soomro, Waqar Khalid, Turgut Tursoy","doi":"10.1016/j.net.2024.08.011","DOIUrl":"https://doi.org/10.1016/j.net.2024.08.011","url":null,"abstract":"Nuclear energy is considered an effective means of enhancing environmental sustainability. Considering this point, this study aims to explore the impact of nuclear energy, financial globalization, technological innovation, and economic growth on ecological sustainability in the top-10 nuclear energy-consuming economies from 1995 to 2020. The load capacity factor is used as a novel proxy for ecological sustainability, explaining how human actions affect ecological sustainability and how nature compensates for human-induced damage. The study employs a novel non-parametric MMQR approach to obtain coefficients across heterogeneous quantiles. The MMQR estimation findings indicate that: (i) nuclear and renewable energy consumption and financial globalization promote environmental sustainability by increasing the LCF; (ii) economic growth degrades ecological sustainability by decreasing the LCF; and (iii) the results from Granger causality suggest a causal link among economic growth, technological innovation, nuclear energy, and LCF. The study recommends that the governments of the top-10 nuclear energy-consuming countries facilitate more investment in green technologies and green energy to achieve environmental sustainability.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207268","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

Exothermic characteristics evaluation of the Pt coated α-Al2O3 catalyst in bed for passive airborne radioactive material reduction system under forced flow conditions 强制流条件下用于被动式气载放射性物质还原系统的床层铂涂层 α-Al2O3 催化剂的放热特性评估

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-05 DOI: 10.1016/j.net.2024.08.009

Hyun Chul Lee, Jungjin Bang, Kiwan Jang, Min Beom Heo, Doo Yong Lee, Daewoo Kim, Chang-Ha Lee

引用次数: 0

Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs 为压水堆中间断口失冷事故编制现象识别和排序表（PIRT）

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-05 DOI: 10.1016/j.net.2024.08.010

Hae Min Park, Jong Hyuk Lee, Chiwoong Choi, Kwi-Seok Ha, Byung Hyun You, Jaeseok Heo, Kyung Doo Kim, Sung Won Bae, Seung Wook Lee, Dong Hyuk Lee, Sang Ik Lee, Chan Eok Park, Bub Dong Chung, Kwang Won Seul

{"title":"Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs","authors":"Hae Min Park, Jong Hyuk Lee, Chiwoong Choi, Kwi-Seok Ha, Byung Hyun You, Jaeseok Heo, Kyung Doo Kim, Sung Won Bae, Seung Wook Lee, Dong Hyuk Lee, Sang Ik Lee, Chan Eok Park, Bub Dong Chung, Kwang Won Seul","doi":"10.1016/j.net.2024.08.010","DOIUrl":"https://doi.org/10.1016/j.net.2024.08.010","url":null,"abstract":"Recent safety issues such as cladding oxidation and fuel fragmentation, relocation and dispersal (FFRD) make the loss-of-coolant accident (LOCA) acceptance criteria more difficult to be satisfied. To obtain the adequate safety margin and more economical use of the nuclear power plant, re-classification of LOCAs for Korean operating PWRs is now under consideration to exclude the large break LOCA (LBLOCA) from the design basis accidents (DBAs). Therefore, the intermediate break LOCA (IBLOCA) might become the limiting break size of concern in the LOCA analysis. To accomplish this reform of LOCA classification, an extensive understanding of IBLOCA is crucial, and the applicability of safety analysis code should be confirmed. For this purpose, IBLOCA PIRT was developed. The PIRT panel was organized and the general process of the PIRT development established by Wilson and Boyack (1998) was adopted to develop the IBLOCA PIRT. Based on IBLOCA analyses using the safety and performance analyzing code (SPACE), the PIRT panel defined the temporal phases, systems, components and possible phenomena during an IBLOCA. For all possible phenomena, the relative importance and the knowledge level were determined for each component and each phase via discussions among PIRT panel members. For phenomena having relatively high importance, a code validation matrix was also developed. The results of the IBLOCA PIRT will be used to improve the SPACE code for IBLOCA application and resolve future regulatory issues.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207275","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

Tracer transport in fractured porous media: Distribution of tracer concentration within the rock matrix and the implementation of time domain random walk algorithm 断裂多孔介质中的示踪剂传输：岩石基质中示踪剂浓度的分布与时域随机行走算法的实施

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-05 DOI: 10.1016/j.net.2024.08.007

Qing Zhao, Shuo Meng, Longcheng Liu

引用次数: 0

Scale effect for hydraulic model of a mixed flow nuclear main pump 混流式核主泵水力模型的规模效应

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-05 DOI: 10.1016/j.net.2024.08.006

Tao Zhou, Yong Zhu, Shengnan Tang

{"title":"Scale effect for hydraulic model of a mixed flow nuclear main pump","authors":"Tao Zhou, Yong Zhu, Shengnan Tang","doi":"10.1016/j.net.2024.08.006","DOIUrl":"https://doi.org/10.1016/j.net.2024.08.006","url":null,"abstract":"Optimizing the hydraulic components of nuclear main pump (NMP) and conducting performance verification is crucial. Due to the large size of the real NMP, the strict requirements of the operation and the high test-cost, there are many difficulties in the real test. The mixed flow NMP is taken as the research object, and the CAP1400 NMP is selected as the prototype pump (PP). The model pumps (MPs) with varying scales are established based on the similarity conversion algorithm (SCA). Then, the influence of different scales on the hydraulic performance and internal flow field is investigated and compared. It is demonstrated that the predicted value of head is 4 % higher than the design value at the design operating point, and the maximum efficiency point is close to the design operating point. In the range of full flow conditions, the head, hydraulic efficiency, impeller efficiency, guide vane energy loss, internal flow field, and vorticity distribution of PP and MPs are basically consistent with the trend of flow rate variations. The PP and MPs conform to the SCA. The hydraulic design and performance optimization of NMP are achieved by using the model proportional scaling approach.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207272","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

Unveiling the potential of Nd2O3 in optimizing the radiation shielding performance of B2O3–TiO2–BaO–ZnO-Nd2O3 glasses 揭示 Nd2O3 在优化 B2O3-TiO2-BaO-ZnO-Nd2O3 玻璃辐射屏蔽性能方面的潜力

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-03 DOI: 10.1016/j.net.2024.08.004

Maryam Al Huwayz, Aljawhara H. Almuqrin, F.F. Alharbi, M.I. Sayyed, B. Albarzan

{"title":"Unveiling the potential of Nd2O3 in optimizing the radiation shielding performance of B2O3–TiO2–BaO–ZnO-Nd2O3 glasses","authors":"Maryam Al Huwayz, Aljawhara H. Almuqrin, F.F. Alharbi, M.I. Sayyed, B. Albarzan","doi":"10.1016/j.net.2024.08.004","DOIUrl":"https://doi.org/10.1016/j.net.2024.08.004","url":null,"abstract":"This research focuses on the preparation of a new glass system designed specifically for applications in radiation shielding materials. These glasses are based on the general formula (56-x)BO–10TiO–8BaO–27ZnO-(x-1)NdO, where x takes the values of 2, 4, 6 and 8 mol%. For the examination of the designed glasses' radiation attenuation performance, Phy-X software was used, which is a useful approach for predicting the linear attenuation coefficient (LAC), the half value layer (HVL), and effective atomic number. The LAC decreases from 1.489 cm to 0.551 cm for the glass with x = 1 mol%, while the glass with 7 mol% NdO saw a decrease in the LAC from 2.483 cm to 0.718 cm. Introducing NdO increases the glasses' LAC, suggesting enhanced radiation shielding performance. Also, NdO addition influences the HVL within the glasses, with higher content reducing the HVL. At 0.122 MeV, the HVL and tenth value layer (TVL) are 0.456 and 1.546 cm, respectively. At 0.245 MeV, the TVL is about 3.32 times higher than the HVL. The lowest mean free path (MFP) is found at 0.122 MeV, which varies between 0.672 cm for Nd1 and 0.403 cm for Nd4.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207273","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

Influence of dissolved hydrogen and IG Cr carbide on the oxidation behavior of Alloy 600 in hydrogenated primary water 溶解氢和 IG 碳化铬对合金 600 在氢化原水中氧化行为的影响

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-03 DOI: 10.1016/j.net.2024.08.003

Yun Soo Lim, Dong Jin Kim, Sung Woo Kim, Seong Sik Hwang, Sung Hwan Cho, Hong Pyo Kim

{"title":"Influence of dissolved hydrogen and IG Cr carbide on the oxidation behavior of Alloy 600 in hydrogenated primary water","authors":"Yun Soo Lim, Dong Jin Kim, Sung Woo Kim, Seong Sik Hwang, Sung Hwan Cho, Hong Pyo Kim","doi":"10.1016/j.net.2024.08.003","DOIUrl":"https://doi.org/10.1016/j.net.2024.08.003","url":null,"abstract":"The internal oxidation (IO) and preferential intergranular oxidation (PIO) behavior of Alloy 600 depending on the dissolved hydrogen (DH) content and the IG Cr carbide in hydrogenated primary water were characterized in detail using analytical electron microscopy techniques. The oxidation layer was unstable when the DH concentration was such that Ni was in the vicinity of Ni/NiO equilibrium and it could easily be peeled off. Hence, the grain boundaries of the bare metal were attacked. PIO occurred and Cr-rich oxide identified as CrO was formed at the oxidized grain boundary. NiO emerged when the DH concentration was such that Ni was in an oxidizing state, whereas Ni enrichment occurred inside the oxidized grain boundary when the DH concentration was such that Ni was in a reducing state with respective to Ni/NiO equilibrium. The IG Cr carbide strongly affected the PIO behavior by means of the consumption of oxygen penetrating into the grain boundary. The depth of the IO layer decreased as the DH concentration increased. The different oxidation behaviors depending on the DH content and IG Cr carbide are believed to affect the PWSCC resistance of Alloy 600 significantly.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141940106","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

Technical studies about the prestressed insulation cylinder of HL-3 tokamak's center-post 有关 HL-3 托卡马克中柱预应力绝缘筒的技术研究

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-03 DOI: 10.1016/j.net.2024.08.001

Yin Qiu, Ming Li, Xiaolong Liu, Qinghua Ren, Tao Lin, Jian Liu

引用次数: 0