Annals of Nuclear Energy最新文献_第9页

Steady-state analysis of Xi’an Pulse Reactor based on the multi-physics coupling method 基于多物理场耦合方法的西安脉冲反应堆稳态分析

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-18 DOI: 10.1016/j.anucene.2024.110922

Tianliang Hu , Duoyu Jiang , Xinyi Zhang , Zhaohao Wang , Lipeng Wang , Lu Cao , Da Li , Lixin Chen

引用次数: 0

Applicability domain and gaps of SNF decay heat validation data – A similarity-based approach 核燃料衰变热验证数据的适用领域和差距--基于相似性的方法

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-18 DOI: 10.1016/j.anucene.2024.110905

Ahmed Shama , Stefano Caruso , Dimitri Rochman

{"title":"Applicability domain and gaps of SNF decay heat validation data – A similarity-based approach","authors":"Ahmed Shama , Stefano Caruso , Dimitri Rochman","doi":"10.1016/j.anucene.2024.110905","DOIUrl":"10.1016/j.anucene.2024.110905","url":null,"abstract":"<div><p>Decay heat measurements on spent nuclear fuel (SNF) provide a basis for code validation. Their applicability domain (AD) and gaps, which are the focus of this study, are not commonly discussed in the literature. The analyzed validation data are based on measurements at the Clab facility and on calculations using the Polaris and ORIGEN codes of the SCALE code system. Bias-predicting machine learning (ML) models are applied: random forest and weighted k-nearest neighbors. The models weigh the similarity between the cases, expressed using correlations. The learning curves are studied by examining the prediction error versus the sample size and the similarity coefficient. The obtained error reduction at higher similarity coefficients supports the argument that the similarity or correlation is informative. However, a marginal error reduction is expected from increasing the validation data size from its current status. Following this, a validation AD is proposed as a range of SNF characteristics within which the validation data and the ML models are observed and tested. Within the AD, different levels of error, i.e., safety margins and conservatism, were evaluated. Beyond the AD, validation gaps exist. Examination of light-water reactor SNF applications indicates that the validation coverage is absent in both MOX fuel and short cooling, diminishes rapidly at higher burnup for low-enrichment fuel, and extends with burnup for high-enrichment cases. Additional measurements are justified to reduce conservatism or achieve validation coverage in applications. A case study of typical UO<sub>2</sub> and MOX SNF applications is analyzed. It is shown that a few tens of optimally selected measurements from both SNF types are necessary to complete validation coverage in numerous applications.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S0306454924005681/pdfft?md5=55d8e2f442073aa564f9095ccd7b7e04&pid=1-s2.0-S0306454924005681-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142241591","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

Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors 铅冷快堆氧化腐蚀和传热耦合分析

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-16 DOI: 10.1016/j.anucene.2024.110919

Yan Zhang , Bo Wang , Dalin Zhang , Chenglong Wang , Yang Yang , Zhengrong Guo , Wenxi Tian , Guanghui Su , Suizheng Qiu

{"title":"Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors","authors":"Yan Zhang , Bo Wang , Dalin Zhang , Chenglong Wang , Yang Yang , Zhengrong Guo , Wenxi Tian , Guanghui Su , Suizheng Qiu","doi":"10.1016/j.anucene.2024.110919","DOIUrl":"10.1016/j.anucene.2024.110919","url":null,"abstract":"<div><p>The coupled code LETHAC-Oxide is developed for analysis of thermal–hydraulic and safety characteristics in lead-cooled fast reactors, considering the impact of oxidation corrosion during prolonged operation. Based on experimental data from CORRIDA, Tsu-2M, and SM-1 facility, the oxidation model is well verified. The reactor concepts LESMOR and BREST-OD-300 are modeled, and the results show that the oxide layer significantly influences heat transfer, particularly at higher temperatures. A comparison between LESMOR and BREST-OD-300 demonstrates that a 95 °C difference in average system temperature will cause 14 times increase in oxide layer thickness and 7 times decrease in steam generator heat exchange capability. Conclusively, LESMOR forms a protective oxide film after a refueling cycle, offering structural material protection without major heat transfer impact. In contrast, BREST-OD-300 shows a substantial increase in cladding temperature and decrease in heat transfer capacity. This result underscores the necessity of oxygen control technology to mitigate risks associated with oxidation corrosion, providing valuable insights for optimal reactor performance and safety.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142241590","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 study on the optimization through the evaluation of radiation exposure by scenarios during steam generator dismantling 通过评估蒸汽发生器拆除过程中的辐照情况进行优化的研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-15 DOI: 10.1016/j.anucene.2024.110901

Jonghyun Shin , Donggyun Lee , Seokyoung Ahn , Dae-Won Cho

{"title":"A study on the optimization through the evaluation of radiation exposure by scenarios during steam generator dismantling","authors":"Jonghyun Shin , Donggyun Lee , Seokyoung Ahn , Dae-Won Cho","doi":"10.1016/j.anucene.2024.110901","DOIUrl":"10.1016/j.anucene.2024.110901","url":null,"abstract":"<div><p>Steam generator (SG) replacements in South Korea began with the Kori No. 1 unit in 1998 due to performance degradation. Currently, 20 steam generators have been replaced in total. While additional decommissioning of dozens of steam generator will be required soon due to life-expiration of several nuclear power plants, there has been no actual dismantling performance of steam generators yet, and the replaced decommissioned steam generators are currently stored in intermediate storage facilities. To minimize waste volume and facilitate site reuse, it’s necessary to proactively dismantle steam generators. These components are less radioactively contaminated and easier to dismantle compared to primary equipment like reactors. Additionally, securing related dismantling technology is essential for managing future replacements or equipment that has been stored. Establishing a process scenario about where and how the steam generator will be safely dismantled is important. It is necessary to analyze the advantages and disadvantages of each scenario to study the timing, location, and method of dismantling, and to develop an optimal process scenario through analysis of worker radiation exposure and dismantling costs. For this purpose, simulations were conducted on the radiation dose to workers according to the timing and method of dismantling, using 3D dismantling simulation software developed by Cyclife Digital Solutions, a subsidiary of French EDF, and the results were reviewed by mathematically modeling and analyzing the radiation doses exposed to workers over the years using an exponential decay model.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142233651","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

Experimental study on CHF enhancement of different oxidized surfaces of low carbon steel in nanofluid 低碳钢不同氧化表面在纳米流体中增强 CHF 的实验研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-15 DOI: 10.1016/j.anucene.2024.110923

Xiaojia Li , Xiaoqiang He , Chong Chen , Dongqing Wang , Binghuo Yan , Laishun Wang

{"title":"Experimental study on CHF enhancement of different oxidized surfaces of low carbon steel in nanofluid","authors":"Xiaojia Li , Xiaoqiang He , Chong Chen , Dongqing Wang , Binghuo Yan , Laishun Wang","doi":"10.1016/j.anucene.2024.110923","DOIUrl":"10.1016/j.anucene.2024.110923","url":null,"abstract":"<div><p>Considerable research has been undertaken to explore the use of nanofluids for augmenting the critical heat flux in the in-vessel retention (IVR) strategy deployed in reactors, demonstrating significant improvements in CHF. However, it is important to consider the potential bias in previous studies on surface CHF due to the oxidation of low carbon steel, which is commonly used in reactor vessels, in both air and water under real-life conditions. This study represents the initial investigation into the oxidation behavior of low carbon steel in an air environment, followed by subsequent boiling in water. The results indicate that when the mild steel surface is pre-oxidized in air, the CHF value in deionized water decreases. However, this effect is not readily apparent in nanofluids. Consequently, it suggests that CHF under real operational conditions could be lower than anticipated. Additionally, nanofluids significantly increase the CHF of surface, however, the enhancement of CHF for oxidized surfaces in water is not as pronounced, a point which has never been mentioned by researchers. The mechanisms of surface oxidation and nanofluid-induced CHF enhancement are explained. Consequently, this paper provides important reference value for studying the application of nanofluids in IVR accidents.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142233650","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

Research on core thermal hydraulic parameters prediction based on the improved GAN method and combined ANN model 基于改进的 GAN 方法和组合 ANN 模型的岩心热工水力参数预测研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-14 DOI: 10.1016/j.anucene.2024.110913

Zhu Yuhan , Chu Jiru , Wang Bo , Hu Shaochun , Wang Weibing , Zhang Jiayi

{"title":"Research on core thermal hydraulic parameters prediction based on the improved GAN method and combined ANN model","authors":"Zhu Yuhan , Chu Jiru , Wang Bo , Hu Shaochun , Wang Weibing , Zhang Jiayi","doi":"10.1016/j.anucene.2024.110913","DOIUrl":"10.1016/j.anucene.2024.110913","url":null,"abstract":"<div><p>This research presents advanced methods of data processing as tools applicable in nuclear engineering. Three methods-autoencoder, random forest and multilayer perceptron were considered for the testing. The multi-layer perceptron (MLP) method preserved best the structure of the data. A better generative adversarial network (GAN) based on the Wasserstein distance was implemented for data generation, which overcomes the issues of gradient vanishing and mode collapse prevailing in common GANs. While examining the generated data, advanced statistical and machine learning techniques were applied to minutely compare the generated and original data. Data forecasting applied a combined model of MLP, convolutional neural network (CNN), and recurrent neural networks (RNN). With limited-memory broyden-fletcher-goldfarb-shanno (LBFGS) optimization algorithm being combined with bayesian optimization, there was significant improved prediction of core thermal hydraulic parameters. Meanwhile, this research provides important techniques to deal with challenges of nuclear engineering data which further impacts the field of nuclear engineering.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142232114","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

Modelling research and performance analysis on a megawatt-level helium-xenon gas cooled small reactor based on the thermal-hydraulic constraints 基于热-水力约束条件的兆瓦级氦-氙气冷小型反应堆模型研究与性能分析

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-14 DOI: 10.1016/j.anucene.2024.110921

Wenxuan Ju , Kewei Ning , Fulong Zhao , Ruibo Lu , Hui Bao , Xu Wang , Sichao Tan

{"title":"Modelling research and performance analysis on a megawatt-level helium-xenon gas cooled small reactor based on the thermal-hydraulic constraints","authors":"Wenxuan Ju , Kewei Ning , Fulong Zhao , Ruibo Lu , Hui Bao , Xu Wang , Sichao Tan","doi":"10.1016/j.anucene.2024.110921","DOIUrl":"10.1016/j.anucene.2024.110921","url":null,"abstract":"<div><p>A conceptual design scheme of helium-xenon gas-cooled fast reactor core consisting of hexagonal prismatic fuel assemblies with a thermal power of 6 MW was proposed. The geometric parameters of the core were determined based on the relationship between hydraulic diameter and inlet velocity of fuel elements with restrain of allowable pressure drop and maximum fuel surface temperature. Thermal performance of individual fuel elements and the cooling effect of helium-xenon channels within the reflector layer were analyzed. Channels for helium-xenon gas mixture were added to reduce the surface temperature outside the reflector layer.</p><p>The computational results indicate that the operational burnup of the reactor can reach 40.88 MW d/kg. The graphite rods added to the core collectively contribute 1404 pcm reactivity, achieving the effect of reducing fuel loading and increasing safety margins in water flooding accidents. The helium-xenon gas mixture reduces the reflector layer temperature by approximately 48.88 %.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142232320","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

Neutronics analysis of a research reactor using a two-step method with the superhomogenization method 采用两步法和超均质法对研究用反应堆进行中子学分析

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-13 DOI: 10.1016/j.anucene.2024.110912

Chixu Luo, Mingrui Yang, Qing Zhu, Chaoyuan Zhang, Xiaojing Liu, Tengfei Zhang

{"title":"Neutronics analysis of a research reactor using a two-step method with the superhomogenization method","authors":"Chixu Luo, Mingrui Yang, Qing Zhu, Chaoyuan Zhang, Xiaojing Liu, Tengfei Zhang","doi":"10.1016/j.anucene.2024.110912","DOIUrl":"10.1016/j.anucene.2024.110912","url":null,"abstract":"<div><p>Research reactors are characterized by significant neutron leakage, tight neutron coupling, and complex core geometries, which make accurate neutronics calculations using the two-step method challenging. This paper analyzes and quantifies the errors introduced by the two-step method for research reactor neutronics calculations. Based on the LVR-15 research reactor, the effects of several key factors, such as the number of energy groups, the homogenization model, and the S<sub>N</sub> order, are studied in detail by comparing the computed <em>k</em><sub>eff</sub> and power with reference values. The numerical results indicate that the factors affecting calculation accuracy, in descending order of impact, are the number of energy groups, the homogenization model, and the S<sub>N</sub> order. The number of energy groups has the most significant impact on calculation accuracy. Specifically, using too few energy groups, such as 2-group energy structures, leads to significant overestimations of <em>k</em><sub>eff</sub>. To further improve accuracy, an improved superhomogenization (SPH) method is proposed. It can stably maintain the <em>k</em><sub>eff</sub> error below 500 pcm and reduce power prediction errors from 3.08 ∼ 4.67 % and 1.69 ∼ 2.80 % to 1.40 ∼ 3.49 % and 0.60 ∼ 1.98 % in the control-rod-in and control-rod-out cases, respectively. These findings provide valuable reference guidelines for other researchers aiming to achieve more accurate research reactor neutronics calculations based on the two-step method.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142228701","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

The energy dependence of the temporal parameters of delayed neutrons from the neutron-induced fission of 235U in the energy range from 0.4 to 8 MeV 中子诱发 235U 裂变产生的延迟中子的时间参数在 0.4 至 8 MeV 能量范围内的能量依赖性

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-13 DOI: 10.1016/j.anucene.2024.110904

D.E. Gremyachkin, A.S. Egorov, K.V. Mitrofanov, V.F. Mitrofanov, V.M. Piksaikin, I.P. Bondarenko

{"title":"The energy dependence of the temporal parameters of delayed neutrons from the neutron-induced fission of 235U in the energy range from 0.4 to 8 MeV","authors":"D.E. Gremyachkin, A.S. Egorov, K.V. Mitrofanov, V.F. Mitrofanov, V.M. Piksaikin, I.P. Bondarenko","doi":"10.1016/j.anucene.2024.110904","DOIUrl":"10.1016/j.anucene.2024.110904","url":null,"abstract":"<div><p>In the present paper the results are discussed on the relative abundances of DN and the half-lives of their precursors from the neutron induced fission of <sup>235</sup>U in the energy range 0.4–8 MeV which have been measured on a modified experimental set-up of the Institute for Physics and Power Engineering (IPPE). The obtained data are compared with the appropriate experimental data by other authors and the data obtained by the summation method and the data presented in the evaluated data libraries JEFF, JENDL, and ENDF/B. The comparison was made in the terms of the average half-life of delayed neutron precursors < T<sub>1/2</sub>(E<sub>n</sub>)>. The obtained data < T<sub>1/2</sub>(E<sub>n</sub>) > were used also for the estimation of the energy dependence of the total DN yield ν<sub>d</sub>(E<sub>n</sub>) from the neutron-induced fission of <sup>235</sup>U on the basis of the correlation properties of delayed neutrons. The obtained total DN yield is compared with available in the open literature data of different origin. The observed features of the obtained ν<sub>d</sub>(E<sub>n</sub>) data most likely indicates that the energy dependence ν<sub>d</sub>(E<sub>n</sub>) is largely governed by the chance structure of the <sup>235</sup>U fission cross-section and to a lesser extent by the odd–even and other effects. The data on the relative abundances and the half-lives of delayed neutron precursors as well as the total delayed neutron yield for <sup>235</sup>U are important for both the safe operation of power reactors and validation of the energy dependence of fission product yields.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142228699","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 on the characteristics of the LBE thermal stratification in a scaled-down hot pool 缩小热池中 LBE 热分层特征的数值研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2024-09-13 DOI: 10.1016/j.anucene.2024.110900

Wenbo Li , Yunqing Bai , Danna Zhou , Wendong Li , Dajian Yu , Yang Li

引用次数: 0