Annals of Nuclear Energy最新文献

{"title":"Review on development status of comprehensive prevention and control technology for disaster-causing floating bodies at water intake of nuclear power plants","authors":"Yingying Zheng ,&nbsp;Rongyong Zhang ,&nbsp;Yun Long ,&nbsp;Xinshu Jiang ,&nbsp;Rongsheng Zhu ,&nbsp;Ji Xing","doi":"10.1016/j.anucene.2024.111087","DOIUrl":"10.1016/j.anucene.2024.111087","url":null,"abstract":"<div><div>Nuclear energy, classified as a clean energy source, enjoys extensive application in numerous countries worldwide. In recent years, the growth rate of marine organisms has accelerated, resulting in the formation of large aggregations of marine organisms and other large congregations that have the potential to obstruct the cold source water intake system of nuclear power plants. The safety situation about the cold source is of significant concern. This paper presents a summary of water intake safety events at nuclear power plants around the world in recent years. It also analyzes the current status of comprehensive prevention and control technology for disaster-causing floating bodies at nuclear power plants’ water intakes. The analysis is based on the latest developments in global nuclear power technology. This study provides a comprehensive overview of the advancements in fine offshore monitoring and early warning systems, passive interception techniques for open channel dredging, the evolution of active defense measures, the development of composite water intake open channel structures, bubble curtain interception methods, cutting and grinding techniques, and the subsequent transportation of marine organisms. Nevertheless, shortcomings remain in the water intake safety of nuclear power plants. These include an inadequate design basis for water intake open channels and sewage interception networks, as well as deficiencies in marine organism early warning and monitoring equipment and layout. Furthermore, the issue of sea ice represents a novel challenge confronting the nuclear power industry in coastal regions situated at high latitudes. Therefore, it is essential to undertake research and implement improvements to the comprehensive technology used to prevent and control water intake safety in nuclear power plants. It is imperative to provide robust backing for the long-term advancement of nuclear power technology.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111087"},"PeriodicalIF":1.9,"publicationDate":"2024-12-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142758982","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}

{"title":"Validating automated resonance evaluation with synthetic data","authors":"Oleksii Zivenko ,&nbsp;Noah A.W. Walton ,&nbsp;William Fritsch ,&nbsp;Jacob Forbes ,&nbsp;Amanda M. Lewis ,&nbsp;Aaron Clark ,&nbsp;Jesse M. Brown ,&nbsp;Vladimir Sobes","doi":"10.1016/j.anucene.2024.111081","DOIUrl":"10.1016/j.anucene.2024.111081","url":null,"abstract":"<div><div>The integrity and precision of nuclear data are crucial for a broad spectrum of applications, from national security and nuclear reactor design to medical diagnostics, where the associated uncertainties can significantly impact outcomes. A substantial portion of uncertainty in nuclear data originates from the subjective biases in the evaluation process, a crucial phase in the nuclear data production pipeline. Recent advancements indicate that automation of certain routines can mitigate these biases, thereby standardizing the evaluation process and enhancing reproducibility. This research aims to provide a methodology, framework, and metrics for the validation of automated nuclear data evaluation software leveraging high-quality synthetic data that closely mimic real experimental observables. An introduced error metric provides a scale and intuitive measure of the evaluation quality by quantifying the estimate’s accuracy and performance across the specified energy range. Synthetic data provides access to experimental observables and underlying resonance parameters, enabling comparison of different evaluations. The methodology is demonstrated using Ta-181 isotope data in the resolved resonance region. The Automated Resonance Identification Subroutine (ARIS), which operates without prior resonance information, was used to test and showcase the framework’s capabilities utilizing the proposed error metrics. The results demonstrate the effectiveness of the proposed approach and framework for optimizing software parameters and testing hypotheses through “what-if” controlled experiments, such as modifying assumptions about experimental conditions or average resonance parameters.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111081"},"PeriodicalIF":1.9,"publicationDate":"2024-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142756924","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}

{"title":"Investigation on heat split in a vertical 3 × 3 dual-cooled annular rod bundle","authors":"Miao Gui ,&nbsp;Jingxin Wang ,&nbsp;Shan Zhou ,&nbsp;Yu Liu ,&nbsp;Jianqiang Shan ,&nbsp;Yu Liang ,&nbsp;Pan Wu","doi":"10.1016/j.anucene.2024.111082","DOIUrl":"10.1016/j.anucene.2024.111082","url":null,"abstract":"<div><div>Single-phase heat transfer experiment in a 3 × 3 dual-cooled annular rod bundle was performed to study the heat split behavior and evaluate the applicability of heat transfer correlations to annular fuel. The parametric effects on heat split were investigated. The results showed that the heat split obviously increased with the flow split, and slightly increased with increasing inlet temperature and heating power. The thermal-conduction resistances of gaps played a leading role in heat split mechanism and the convective heat transfer was the secondary factor affecting the heat split. The applicability of heat transfer correlations was assessed by the experimental data. The predictive performance was significantly improved when replacing the hydraulic equivalent diameter by the heated equivalent diameter in the Nusselt number calculation. The DB and El-Genk correlations had the best predictive effect on the heat transfer in the external channel, with the MAE of 0.082 and 0.094 respectively.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111082"},"PeriodicalIF":1.9,"publicationDate":"2024-11-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142746079","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}

{"title":"Impact of temperature- and phase-dependent zirconium hydride phonons on criticality","authors":"Amelia Trainer ,&nbsp;Benoit Forget ,&nbsp;Jesse Holmes ,&nbsp;Jonathan Wormald ,&nbsp;Michael Zerkle","doi":"10.1016/j.anucene.2024.111034","DOIUrl":"10.1016/j.anucene.2024.111034","url":null,"abstract":"<div><div>Zirconium hydride is a solid moderator material that has a high (albeit variable) hydrogen content. Proper modeling of the thermal neutron population in zirconium hydride requires that the thermal neutron scattering law be used, which incorporates the material structure into the cross section. In the incoherent approximation, this scattering law may be calculated using a material’s phonon distribution and other material parameters. Historically, the partial phonon distributions for zirconium hydride (ZrH<span><math><msub><mrow></mrow><mrow><mi>x</mi></mrow></msub></math></span>) have often been assumed to be independent of hydrogen content, crystalline phase, and temperature. The present work aims to relax this approximation by generating phonon distributions using molecular dynamics while varying (1) the hydrogen content, (2) crystalline phase, and (3) material temperature. Through this work, hydrogen content and crystalline phase have shown to have mild impacts on the vibrational structure, while temperature appears to hold strong influence over the vibrational properties of the materials considered. Temperature-dependent H(ZrH<span><math><msub><mrow></mrow><mrow><mi>x</mi></mrow></msub></math></span>) phonon distributions for <span><math><mi>δ</mi></math></span>-ZrH_1.67, <span><math><mi>ϵ</mi></math></span>-ZrH_1.82, and <span><math><mi>ϵ</mi></math></span>-ZrH₂ were tested on models of a TRIGA reactor and a SNAP reactor, showing how material-specific vibrational models can noticeably influence <span><math><msub><mrow><mi>k</mi></mrow><mrow><mi>eff</mi></mrow></msub></math></span>, flux distributions, and reactivity coefficients.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111034"},"PeriodicalIF":1.9,"publicationDate":"2024-11-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142746078","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}

{"title":"Application of data partitioned Kriging algorithm with GPU acceleration in real-time and refined reconstruction of three-dimensional radiation fields","authors":"Ningbiao Xiao,&nbsp;Jinsen Guo,&nbsp;Zijia Kuang,&nbsp;Wei Wang","doi":"10.1016/j.anucene.2024.111047","DOIUrl":"10.1016/j.anucene.2024.111047","url":null,"abstract":"<div><div>Accurately assessing personal radiation doses in real radiation environments like nuclear power plants requires precise and real-time reconstruction of three-dimensional radiation fields. The Kriging algorithm, known for its accuracy in spatial interpolation, provides a promising approach for this task. However, its computational demands can be significant, especially in real-time scenarios. To address this, we enhance the Kriging algorithm with GPU acceleration and data partitioning strategies, enabling efficient and accurate reconstruction of three-dimensional nuclear radiation fields. Using Fluka software for Monte Carlo simulations, we generated a virtual radiation field of dimensions 5 m <span><math><mo>×</mo></math></span> 5 m <span><math><mo>×</mo></math></span> 5 m for a single-source, unshielded scenario, and a field of dimensions 20 m <span><math><mo>×</mo></math></span> 6 m <span><math><mo>×</mo></math></span> 8 m for a multi-source, shielded scenario. Using the simulated data, we compared the prediction accuracy of the improved algorithm with the conventional Kriging algorithm and further explored factors influencing the acceleration ratio of the improved algorithm. The results indicate that the GPU-accelerated and data-partitioned Kriging algorithm achieves nearly identical accuracy compared to the traditional method. In the single-source, unshielded scenario, with more than 343 known (measurement) points and predicting <span><math><mrow><mn>95</mn><mo>×</mo><mn>95</mn><mo>×</mo><mn>95</mn><mo>=</mo></mrow></math></span> 857,375 points, the prediction accuracy remains above 92.25%. In the multi-source, shielded scenario, with more than 8000 known (measurement) points and predicting <span><math><mrow><mn>95</mn><mo>×</mo><mn>95</mn><mo>×</mo><mn>95</mn><mo>=</mo></mrow></math></span> 857,375 points, the prediction accuracy remains above 91.17%. The acceleration performance of the improved algorithm is consistent across both scenarios, with the acceleration ratio increasing as the number of known and predicted points grows, reaching approximately 20 for smaller datasets and up to 93 for larger datasets. Additionally, the acceleration effect of the improved algorithm varies with data partition size, initially increasing and then decreasing as the partition size increases. When the number of known points is 512 and the number of predicted points is 884,736, the optimal partition size lies between 80,000 and 90,000, resulting in a prediction time of only 0.24 s.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111047"},"PeriodicalIF":1.9,"publicationDate":"2024-11-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142720717","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}

{"title":"Evaluation of uranium-233 neutron capture cross section in keV region","authors":"Naohiko Otuka ,&nbsp;Kenichi Tada ,&nbsp;Oscar Cabellos ,&nbsp;Osamu Iwamoto","doi":"10.1016/j.anucene.2024.110977","DOIUrl":"10.1016/j.anucene.2024.110977","url":null,"abstract":"<div><div>The uranium-233 neutron capture cross section between 3 keV and 1 MeV was evaluated with the alpha value recently measured at the Los Alamos National Laboratory LANCE facility and compiled in the EXFOR library. The obtained capture cross section is systematically lower than those in the latest versions of the major general purpose nuclear data libraries, and the reduction from the JENDL-5 library is close to 50% around 20 keV. The newly evaluated cross section was benchmarked against 166 criticality experiments chosen from the ICSBEP handbook by performing Monte Carlo neutron transport calculation with the JENDL-5 library, and slight reduction of the cumulative chi-square value was achieved by adoption of the newly evaluated capture cross section.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 110977"},"PeriodicalIF":1.9,"publicationDate":"2024-11-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142720716","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}

{"title":"Boiling critical characteristics in narrow rectangular channel under local heat flux concentration conditions","authors":"Kepiao Li ,&nbsp;Kui Zhang ,&nbsp;Tianyi Qi ,&nbsp;Ronghua Chen ,&nbsp;Wenxi Tian ,&nbsp;Suizheng Qiu","doi":"10.1016/j.anucene.2024.111077","DOIUrl":"10.1016/j.anucene.2024.111077","url":null,"abstract":"<div><div>For the establishment of predicting method of local concentrated critical heat flux (CHF) in narrow rectangular channels, and also technical support for the preparation of long-life and high-performance dispersive plate fuel, this work simulates Dry-out type CHF under local concentration of heat flux condition by using Eulerian multiphase model and Enhanced near-wall treatment. The distribution of near-wall temperature and void fraction under different heat flux was calculated by Computational Fluid Dynamics (CFD) method. Dry-out CHF was predicted based on highly and quickly wall temperature rise. The influence of system pressure, mass flow rate and inlet subcooling degree were discussed on Dry-out CHF. Compared with uniform heating, the predicted average heat flux on CHF is lower under local heat flux concentration, and location of CHF is related to the position of heat flux concentration area. This work’s research method in Ansys Fluent could be applied to forecast Dry-out CHF in narrow rectangular channel under local concentration of heat flux condition.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111077"},"PeriodicalIF":1.9,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142720715","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}

{"title":"SCALE inventory and reactivity analysis as part of the Hermes 2021 PSAR review","authors":"Friederike Bostelmann ,&nbsp;Benjamin R. Betzler ,&nbsp;Donny Hartanto ,&nbsp;William A. Wieselquist","doi":"10.1016/j.anucene.2024.111063","DOIUrl":"10.1016/j.anucene.2024.111063","url":null,"abstract":"<div><div>The readiness of SCALE for comprehensive studies of pebble-bed reactors has been demonstrated through detailed analysis of a fluoride salt–cooled, high-temperature pebble-bed reactor (PB-FHR). The methods developed for pebble-bed reactor modeling in SCALE, particularly for inventory generation, have proven effective in gaining insights into the reactor physics of this advanced reactor. Excellent agreement with another code package has been observed, further highlighting SCALE’s strong performance.</div><div>The SCALE results supported the US Nuclear Regulatory Commission’s construction permit application review of the <em>Hermes</em> low-power PB-FHR demonstration reactor. A SCALE model of the Hermes reactor was developed at Oak Ridge National Laboratory using information from the Preliminary Safety Analysis Report (PSAR) and supplemented with publicly available data. SCALE reactivity coefficient simulations reproduced PSAR results within 1<span><math><mi>σ</mi></math></span> statistical uncertainties. Sensitivity studies emphasized the importance of graphite specifications for accurate k_eff predictions.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111063"},"PeriodicalIF":1.9,"publicationDate":"2024-11-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142704187","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}

{"title":"Numerical simulation of impurity particles migration and deposition within the 5 × 5 fuel assembly under nucleate boiling conditions","authors":"Hongkang Tian ,&nbsp;Tenglong Cong ,&nbsp;Maolong Liu ,&nbsp;Mengke Cai ,&nbsp;Zijian Huang ,&nbsp;Hanyang Gu","doi":"10.1016/j.anucene.2024.111076","DOIUrl":"10.1016/j.anucene.2024.111076","url":null,"abstract":"<div><div>Deposition of corrosion products on the cladding surface can cause many problems in PWRs, such as CRUD-induced power shift, localized corrosion, and increased radioactive risk. To gain a deeper understanding of fouling behavior within the fuel assembly, the migration and deposition of impurity particles were investigated with CFD method, where the Eulerian two-fluid model, species transport model, and fouling deposition model are considered. The relationship between fouling deposition rate and thermal–hydraulic parameters was investigated, and the distribution of fouling thickness along both the axial and circumferential directions was analyzed. The results show that the maximum fouling thickness reaches 44 µm in a refueling cycle. Compared with the inner rods, the corner rods have a higher fouling thickness in single-phase region and a lower fouling thickness in nucleate boiling region. The results obtained in this study could provide a reference for the investigation of deposition behavior within the reactor core.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111076"},"PeriodicalIF":1.9,"publicationDate":"2024-11-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142704090","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}

{"title":"Investigation on thermal response of high temperature heat pipe under thermal mismatch conditions","authors":"Zhang Jiarui ,&nbsp;Guo Kailun ,&nbsp;Liu Lining ,&nbsp;Xue Meng ,&nbsp;Wang Chenglong ,&nbsp;Tian Wenxi ,&nbsp;Qiu Suizheng ,&nbsp;Su Guanghui ,&nbsp;Chen Chong","doi":"10.1016/j.anucene.2024.111075","DOIUrl":"10.1016/j.anucene.2024.111075","url":null,"abstract":"<div><div>As an efficient and reliable passive heat transfer equipment, high temperature heat pipes (HTHPs) plays an important role in HTHP solid state reactor system. HTHPs often encounter thermal mismatch in reactor applications, which will lead to capillary action, entrainment, and other characteristics, resulting in HTHP failure due to heat transfer limits. In this paper, the thermal response test of liquid metal HTHP under thermal mismatch conditions is studied, and the simulation test platform of HTHP mismatch is designed and built to measure the important physical parameters. The test results show that the heat transfer performance of the HTHP is the best under the condition of horizontal inclination of 60°, and the condenser power is 5.66 kW. This condition is selected as the reference condition for the transient condition test. When the HTHP experienced a transient power increase, the middle of the evaporator section, as the part with the largest heat flux of heating power, appeared a severe overheating phenomenon. The wall temperature of the evaporator section soared from 750 ℃ to 1050 ℃ in a short time, and the heating rate reached 18.9 ℃/min, which affected the smooth operation of the HTHP. When the HTHP encounters an inclination angle transient increase condition, the entrainment phenomenon is more severe, the temperature fluctuation of the condenser section is intensified, and the heat transfer of the HTHP is in an unstable state. When the HTHP encounters an inclination angle transient decrease condition, the temperature rise of the evaporator section is less than 10 ℃, the temperature at the end of the condenser section is increased, and the start-up performance of the HTHP is improved. In summary, this paper obtains the thermal response rule of HTHPs under thermal mismatch conditions through experimental research, which provides support for the safe application of HTHPs for special equipment.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111075"},"PeriodicalIF":1.9,"publicationDate":"2024-11-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142704034","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}