Journal of Nuclear Engineering and Radiation Science最新文献_第5页

Study On the Step by Step Process and Performance of Laser Welding for the Spent Fuel Pool Floor 乏燃料池底板逐级激光焊接工艺及性能研究

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-07-21 DOI: 10.1115/1.4063008

Le Mei, Xiaochun Zhang, Junbao Zhang, Changlei Shao, Jialei Zhu, Ran Huang, Chongzhi Wu

{"title":"Study On the Step by Step Process and Performance of Laser Welding for the Spent Fuel Pool Floor","authors":"Le Mei, Xiaochun Zhang, Junbao Zhang, Changlei Shao, Jialei Zhu, Ran Huang, Chongzhi Wu","doi":"10.1115/1.4063008","DOIUrl":"https://doi.org/10.1115/1.4063008","url":null,"abstract":"\u0000 In order to realize the steel liner underwater repairing of the spent fuel pool of the third generation nuclear power plant, the laser welding process tests were carried out step by step in three environments: air, shallow water and simulating-repairing of the spent fuel pool floor(high-pressure condition). Through the process optimization, the high-quality forming of the underwater laser welding of duplex stainless steel was realized, and the underwater local dry laser welding process suitable for the spent fuel pool floor of nuclear power plant was developed. The results of nondestructive testing (including visual testing, liquid penetrant testing, ultrasonic testing and radiographic testing) of welding test pieces under three environments were qualified, and the test results of properties (including tensile, impact, bending, intergranular corrosion, ferrite content) meet the standard requirements. The underwater weld performance is similar to that in the air environment, and the weld quality meets the requirements of the spent fuel pool construction standard, laying a technical foundation for the application of the spent fuel pool underwater repairing.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"97 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82441959","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Total Loss of Feedwater Analysis of PWR Using RELAP5 利用RELAP5分析压水堆给水总损失

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Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-07-21 DOI: 10.1115/1.4063009

A. Prošek

{"title":"Total Loss of Feedwater Analysis of PWR Using RELAP5","authors":"A. Prošek","doi":"10.1115/1.4063009","DOIUrl":"https://doi.org/10.1115/1.4063009","url":null,"abstract":"\u0000 In Europe the design extension conditions (DEC) were introduced after the Fukushima Dai-ichi accident as preferred method for giving due consideration to the complex sequences and severe accidents without including them in the design basis conditions. The objective of the study is to determine available elapsed time before core uncovery and needed DEC safety features for total loss of all feedwater (TLOFW) in a two-loop pressurized water reactor. RELAP5/MOD3.3 computer code has been used for calculations. The initiating event for TLOFW are multiple failures in which, besides the loss of main feedwater also the auxiliary feedwater is lost. The scenarios without DEC safety features and the scenarios with DEC safety features assumed have been simulated.\u0000 The results showed that after TLOFW event initiation it is very important to trip the reactor as soon as possible. In case of loss of offsite power the reactor coolant pumps stop and the reactor very quickly trips on low reactor coolant pump flow. When normal operation systems are assumed the reactor trip occurs on low-low steam generator narrow level few tens of seconds after accident initiation, resulting in less time available before core uncovery occurence. The results for TLOFW scenarios with normal operation systems and DEC safety featured assumed demonstrated that secondary side bleed and feed can prevent core uncovery in case when no operator actions are credited before 30 minute. When primary side bleed and feed is used, less time is available for operator actions.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"301 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82871641","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

CFD Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor 小型模块化重水反应堆慢化剂热和流体流动的CFD计算

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-07-21 DOI: 10.1115/1.4063007

T. Kořínek, R. Škoda, M. Lovecký, O. Burian

{"title":"CFD Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor","authors":"T. Kořínek, R. Škoda, M. Lovecký, O. Burian","doi":"10.1115/1.4063007","DOIUrl":"https://doi.org/10.1115/1.4063007","url":null,"abstract":"\u0000 The heavy water reactor concept Teplator is a pressure channel type reactor with independent systems for the primary coolant and the moderator. The present study analyses the low-pressure moderator cooling system of Teplator during full-power operation. The moderator is heated from neutron thermalization, gamma rays absorption, fission product decay and decay of activation products. Additionally, heat transfer from the coolant channels has to be taken in the analyses of the moderator cooling system. Preliminary thermal-hydraulic analyses of the cooling system are supplemented by CFD simulations of heat and fluid flow in the moderator's vessel, emphasizing flow-type regimes. Results from CFD simulations showed that the buoyancy-dominated flow (case MF-22) resulted in a higher thermal stratification and high moderator temperature close to the upper plate of the moderator vessel. The inertia-dominated flow regime MF-90 resulted in good mixing of the moderator and a low thermal stratification in the vessel. Finally, the mid-mass flow rate regime MF-45 was identified as a transitional region from a buoyancy-dominated to a mix-type regime.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"59 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81450350","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A Review of Opportunities and Methods for Recovery of Rhodium from Spent Nuclear Fuel during Reprocessing 乏核燃料后处理中回收铑的机会和方法综述

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Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-07-18 DOI: 10.3390/jne4030034

B. Hodgson, J. Turner, Alistair F. Holdsworth

{"title":"A Review of Opportunities and Methods for Recovery of Rhodium from Spent Nuclear Fuel during Reprocessing","authors":"B. Hodgson, J. Turner, Alistair F. Holdsworth","doi":"10.3390/jne4030034","DOIUrl":"https://doi.org/10.3390/jne4030034","url":null,"abstract":"Rhodium is one of the scarcest, most valuable, and useful platinum group metals, a strategically important material relied on heavily by automotive and electronics industries. The limited finite natural sources of Rh and exponentially increasing demands on these supplies mean that new sources are being sought to stabilise supplies and prices. Spent nuclear fuel (SNF) contains a significant quantity of Rh, though methods to recover this are purely conceptual at this point, due to the differing chemistry between SNF reprocessing and the methods used to recycle natural Rh. During SNF reprocessing, Rh partitions between aqueous nitric acid streams, where its speciation is complex, and insoluble fission product waste streams. Various techniques have been investigated for Rh recovery during SNF reprocessing for over 50 years, including solvent extraction, ion exchange, precipitation, and electrochemical methods, with tuneable approaches such as impregnated composites and ionic liquids receiving the most attention recently, assisted by more the comprehensive understanding of Rh speciation in nitric acid developed recently. The quantitative recovery of Rh within the SNF reprocessing ecosystem has remained elusive thus far, and as such, this review discusses the recent developments within the field, and strategies that could be applied to maximise the recovery of Rh from SNF.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"11 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-07-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79205071","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

9Mv Linac Photo-Neutron Interrogation Of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors 用先进声张力亚稳流体探测器对铀进行9Mv直线光中子探测

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Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-07-11 DOI: 10.1115/1.4062951

N. Boyle, S. Ozerov, C. Harabagiu, R. Taleyarkhan

{"title":"9Mv Linac Photo-Neutron Interrogation Of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors","authors":"N. Boyle, S. Ozerov, C. Harabagiu, R. Taleyarkhan","doi":"10.1115/1.4062951","DOIUrl":"https://doi.org/10.1115/1.4062951","url":null,"abstract":"\u0000 Active special nuclear material (SNM) photoneutron interrogation research with Acoustically Tensioned Metastable Fluid Detector (ATMFD) sensor technology is discussed which provides evidence for enabling real time detection of special nuclear material (SNM) even when deployed under extreme 15,000 R h-1 (9 MeV endpoint) X-ray beams. Experiments to detect 3.2 kg DU are described with use of two designs of the economical E-ATMFD, viz., E-ATMFD.Ver.0 and E-ATMFD.Ver.1, respectively, at standoffs ranging from 0.1 m to 10 m - including with the E-ATMFD directly within the interrogating beam. Under similar conditions and with 100% photon rejection (i.e., 0 cpm with beam on, and w/o SNM), the E-ATMFD.Ver.1 design was shown capable of ~6x (600%) higher gain at ~10x lower drive powers over E-ATMFD.Ver.0 (with beam on and with SNM). The sensitivity gain rises to ~27x (i.e., 2,700%) with the E-ATMFD.Ver.1 operating at 0.99 W and a background count rate of ~1 cpm. The E-ATMFD.Ver.1 demonstrated 100% photon blindness (0 cpm) while operating at ~0.56 W drive power and placed directly within the beam under 15,000 R/h; including the SNM target led to a count rate of up to 50 cpm - revealing the E-ATMFD.Ver.1 as potentially field-capable for detecting U-based SNMs within seconds from photofission neutron signals, even when deployed directly within the interrogating photon beam.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"27 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-07-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88946558","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Multi-Abnormality Attention Diagnosis Model Using One-vs-Rest Classifier in a Nuclear Power Plant 基于一对休息分类器的核电厂多异常注意诊断模型

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-07-08 DOI: 10.3390/jne4030033

Seungyon Cho, Jeonghun Choi, J. Shin, Seung Jun Lee

{"title":"Multi-Abnormality Attention Diagnosis Model Using One-vs-Rest Classifier in a Nuclear Power Plant","authors":"Seungyon Cho, Jeonghun Choi, J. Shin, Seung Jun Lee","doi":"10.3390/jne4030033","DOIUrl":"https://doi.org/10.3390/jne4030033","url":null,"abstract":"Multi-abnormal events, referring to the simultaneous occurrence of multiple single abnormal events in a nuclear power plant, have not been subject to consideration because multi-abnormal events are extremely unlikely to occur and indeed have not yet occurred. Such events, though, would be more challenging to diagnose than general single abnormal events, exacerbating the human error issue. This study introduces an efficient abnormality diagnosis model that covers multi-abnormality diagnosis using a one-vs-rest classifier and compares it with other artificial intelligence models. The multi-abnormality attention diagnosis model deals with multi-label classification problems, for which two methods are proposed. First, a method to effectively cluster single and multi-abnormal events is introduced based on the predicted probability distribution of each abnormal event. Second, a one-vs-rest classifier with high accuracy is employed as an efficient way to obtain knowledge on which particular multi-abnormal events are the most difficult to diagnose and therefore require the most attention to improve the multi-label classification performance in terms of data usage. The developed multi-abnormality attention diagnosis model can reduce human errors of operators due to excessive information and limited time when unexpected multi-abnormal events occur by providing diagnosis results as part of an operator support system.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"13 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90196767","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Implementation Of Solar Salt Properties Into Ariant And Simulation Of Pressurized Loss Of Forced Circulation In A High Temperature Gas-Cooled Small Modular Reactor 太阳盐特性在变型中的实现及高温气冷小型模块堆强制循环压力损失的模拟

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-07-07 DOI: 10.1115/1.4062917

Jason Wu, T. Beuthe, Aleksandar Vasić

引用次数: 0

SNM Radiation Signature Classification Using Different Semi-Supervised Machine Learning Models 基于不同半监督机器学习模型的SNM辐射特征分类

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-07-04 DOI: 10.3390/jne4030032

Jordan R. Stomps, Paul P. H. Wilson, K. Dayman, Michael J. Willis, James M. Ghawaly, Daniel E. Archer

{"title":"SNM Radiation Signature Classification Using Different Semi-Supervised Machine Learning Models","authors":"Jordan R. Stomps, Paul P. H. Wilson, K. Dayman, Michael J. Willis, James M. Ghawaly, Daniel E. Archer","doi":"10.3390/jne4030032","DOIUrl":"https://doi.org/10.3390/jne4030032","url":null,"abstract":"The timely detection of special nuclear material (SNM) transfers between nuclear facilities is an important monitoring objective in nuclear nonproliferation. Persistent monitoring enabled by successful detection and characterization of radiological material movements could greatly enhance the nuclear nonproliferation mission in a range of applications. Supervised machine learning can be used to signal detections when material is present if a model is trained on sufficient volumes of labeled measurements. However, the nuclear monitoring data needed to train robust machine learning models can be costly to label since radiation spectra may require strict scrutiny for characterization. Therefore, this work investigates the application of semi-supervised learning to utilize both labeled and unlabeled data. As a demonstration experiment, radiation measurements from sodium iodide (NaI) detectors are provided by the Multi-Informatics for Nuclear Operating Scenarios (MINOS) venture at Oak Ridge National Laboratory (ORNL) as sample data. Anomalous measurements are identified using a method of statistical hypothesis testing. After background estimation, an energy-dependent spectroscopic analysis is used to characterize an anomaly based on its radiation signatures. In the absence of ground-truth information, a labeling heuristic provides data necessary for training and testing machine learning models. Supervised logistic regression serves as a baseline to compare three semi-supervised machine learning models: co-training, label propagation, and a convolutional neural network (CNN). In each case, the semi-supervised models outperform logistic regression, suggesting that unlabeled data can be valuable when training and demonstrating value in semi-supervised nonproliferation implementations.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"11 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84410960","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors 预测熔盐堆冻结塞开启时间的简单解析模型

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-06-30 DOI: 10.1115/1.4062879

M. Ilham, T. Okawa

引用次数: 0

An Estimation Method For Bias Error Of Measurements By Utilizing Process Data, An Incidence Matrix And A Reference Instrument For Data Validation And Reconciliation 一种利用过程数据、关联矩阵和参考仪器对测量偏差误差进行估计的方法

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-06-29 DOI: 10.1115/1.4062865

A. Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura

{"title":"An Estimation Method For Bias Error Of Measurements By Utilizing Process Data, An Incidence Matrix And A Reference Instrument For Data Validation And Reconciliation","authors":"A. Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura","doi":"10.1115/1.4062865","DOIUrl":"https://doi.org/10.1115/1.4062865","url":null,"abstract":"\u0000 With further applications of AI, IoT, and digital twin technology to plant operation and maintenance, it is becoming increasingly important to ensure data reliability. Data validation and reconciliation (DVR) represents one promising technique to ensure data reliability by minimizing the uncertainty of measurements based on statistics. DVR has been widely applied to nuclear power electrical generation plants in Europe and the United States in recent years. The most important input for DVR analysis is measurement uncertainty. In Japan, performance management of nuclear power plants is often done by measuring condensate flow rate. While the uncertainty of other flowmeters is handled by the JIS standard, the condensate flowmeter is specially calibrated every few cycles. This leads to reduction of effectiveness of DVR analysis due to variations in measurement uncertainty management. To overcome this issue, we propose an estimation method for measurement uncertainty by utilizing process data, an incidence matrix between sensors, and a reference instrument. The conventional method proposed in the previous study only treats the random error. The proposed method quantitatively estimates not only random error but also bias error by considering the uncertainty of the reference instrument. Using several benchmark problems, we found that the proposed method was applicable to various flow conditions, including physically fluctuating flow such as that observed in the feedwater flow in nuclear power plants. We anticipate that the proposed method will promote use of DVR analysis in nuclear power plants in Japan.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"16 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-06-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90490442","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0