Annals of Nuclear Energy最新文献_第10页

The molten salt tritium transport experiment: A pumped fluoride salt loop for hydrogen isotope experimentation 熔盐氚输运实验：用于氢同位素实验的泵浦氟化物盐环

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-19 DOI: 10.1016/j.anucene.2025.111659

Thomas F. Fuerst, Anthony G. Bowers, Hanns A. Gietl, Nicole L. France, L.Shayne Loftus, Adriaan A. Riet, Matthew D. Eklund, Chase N. Taylor, Masashi Shimada

{"title":"The molten salt tritium transport experiment: A pumped fluoride salt loop for hydrogen isotope experimentation","authors":"Thomas F. Fuerst, Anthony G. Bowers, Hanns A. Gietl, Nicole L. France, L.Shayne Loftus, Adriaan A. Riet, Matthew D. Eklund, Chase N. Taylor, Masashi Shimada","doi":"10.1016/j.anucene.2025.111659","DOIUrl":"10.1016/j.anucene.2025.111659","url":null,"abstract":"<div><div>Molten salt reactors and fusion reactors propose to use molten salt as coolants and breeder blanket materials. Tritium, however, poses safety concerns in both reactor types due to its ability to permeate through reactor materials creating the potential for environmental release. This article addresses the tritium transport phenomena in molten salts and presents the design and analysis of the Molten Salt Tritium Transport Experiment (MSTTE). MSTTE is a forced-convection fluoride salt loop intended to measure hydrogen isotope permeation through structural materials in a flowing salt system. Computational fluid dynamics analysis ensures fully developed salt flow in the permeation test section. MSTTE is modeled with MELCOR-TMAP to predict the permeation rate as a function of experimental variables such as source rate, salt flow rate, and salt temperature. Additionally, pressure drop analysis is conducted and finite-element analysis assesses thermal stress during loop operation to ensure the experiment’s safe design.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111659"},"PeriodicalIF":1.9,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144320968","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

Semi-empirical model for resuspension of multilayer sedimentary aerosols in pipes 管道中多层沉积气溶胶再悬浮的半经验模型

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-19 DOI: 10.1016/j.anucene.2025.111652

Peizheng Hu , Zhichao Gao , Yixin Huang , Lili Tong , Xuewu Cao

{"title":"Semi-empirical model for resuspension of multilayer sedimentary aerosols in pipes","authors":"Peizheng Hu , Zhichao Gao , Yixin Huang , Lili Tong , Xuewu Cao","doi":"10.1016/j.anucene.2025.111652","DOIUrl":"10.1016/j.anucene.2025.111652","url":null,"abstract":"<div><div>As a critical phenomenon influencing radioactive release assessment during nuclear severe accidents, aerosol resuspension requires in-depth investigation, as it can affect the accuracy of radioactive release source term assessment. An experimental apparatus has been established and the resuspension of multi-layered sedimentary aerosols have been conducted under turbulent airflow conditions with Reynolds number ranging from 50,000 to 130,000. The experiments indicate that higher friction velocity of turbulent pipe and larger deposited particle size both increase the resuspension rate. Through mechanical fulcrum model analysis, the resuspension characteristics, which encompass the coupling effects of airflow characteristics, particle characteristics and wall characteristics, are revealed by the dimensionless particle diameter <span><math><msubsup><mi>d</mi><mi>p</mi><mo>+</mo></msubsup></math></span> and critical dimensionless particle diameter <span><math><msubsup><mi>d</mi><mrow><mi>p</mi><mn>50</mn></mrow><mo>+</mo></msubsup></math></span>. A semi-empirical aerosol resuspension model satisfying the S-Logistic function relationship is obtained and validated with multiple sets of experimental data, and showing good agreement between the model predictions and the experimental results.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111652"},"PeriodicalIF":1.9,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144313807","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

SPARTA: A flux adjustment methodology to interpret complex experiments 斯巴达：解释复杂实验的通量调整方法

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-19 DOI: 10.1016/j.anucene.2025.111623

Paul A. Ferney, Ben A. Baker, Mark D. DeHart

{"title":"SPARTA: A flux adjustment methodology to interpret complex experiments","authors":"Paul A. Ferney, Ben A. Baker, Mark D. DeHart","doi":"10.1016/j.anucene.2025.111623","DOIUrl":"10.1016/j.anucene.2025.111623","url":null,"abstract":"<div><div>To accurately determine reactivity from a detector count rate, correcting spatial effects is of prime importance. Simulation methodologies are often used for spatial correction, but they may introduce an additional source of uncertainty if the results of the experiment are also used as the input data for the simulation. This work presents a flux adjustment methodology that can infer experimental reactivity and correct spatial effects without the need for a simulation. It can process the detector signal(s) from a complex experiment, such as a heat balance measurement in the Transient Reactor Test Facility (TREAT) in which control rods are continuously adjusted to maintain a constant power. The methodology presented in this work successfully computed the reactivity and the local spatial variation of the flux from a generated signal. It also proved to be robust against noise and errors on kinetic parameters and provided a credible interpretation of a heat balance experiment in TREAT. An efficient flux adjustment method for complex experiments enables better experiment interpretation that is less reliant on nuclear data evaluations.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111623"},"PeriodicalIF":1.9,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144313810","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

Radiological impact assessment of a hypothetical accident at the Zaporizhzhia nuclear power plant 核电厂假想事故的辐射影响评估

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-19 DOI: 10.1016/j.anucene.2025.111680

Kyung-Suk Suh , Sora Kim , Kihyun Park , Byung-Il Min , Yoomi Choi , Jiyoon Kim , Min-Chae Kim , Hyeonjeong Kim , Kyeong-Ok Kim

{"title":"Radiological impact assessment of a hypothetical accident at the Zaporizhzhia nuclear power plant","authors":"Kyung-Suk Suh , Sora Kim , Kihyun Park , Byung-Il Min , Yoomi Choi , Jiyoon Kim , Min-Chae Kim , Hyeonjeong Kim , Kyeong-Ok Kim","doi":"10.1016/j.anucene.2025.111680","DOIUrl":"10.1016/j.anucene.2025.111680","url":null,"abstract":"<div><div>The atmospheric dispersion of radioactive materials and the resulting radiation dose were assessed for a hypothetical accident at the Zaporizhzhia Nuclear Power Plant in Ukraine. The release quantities of <sup>131</sup>I and <sup>137</sup>Cs were assumed to be the same as those released into the atmosphere in the Chernobyl nuclear accident. The evaluation utilized atmospheric dispersion and dose assessment models, both of which are key components of the Radiological Accident Preparedness System in Korea (RAPS-K) developed by the Korea Atomic Energy Research Institute. Simulation results showed that radioactive plumes initially moved to the western across Europe, and later, some plumes were transported to the Asia due to westerly winds. Dose assessments revealed that effective radiation doses were showed above 1 mSv in certain areas near the Zaporizhzhia plant, while radiation exposure remained below 0.1 mSv across the rest of Europe, Asia, and North America. Especially, the thyroid dose due to <sup>131</sup>I was presented about 19 mSv and 29 mSv, respectively in Kyiv and Odesa of Ukraine.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111680"},"PeriodicalIF":1.9,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144321027","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

Underlying mathematical relations for COMET calculations in problems with global symmetry 整体对称问题中彗星计算的基本数学关系

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-19 DOI: 10.1016/j.anucene.2025.111639

Dingkang Zhang, Farzad Rahnema

{"title":"Underlying mathematical relations for COMET calculations in problems with global symmetry","authors":"Dingkang Zhang, Farzad Rahnema","doi":"10.1016/j.anucene.2025.111639","DOIUrl":"10.1016/j.anucene.2025.111639","url":null,"abstract":"<div><div>This paper derives the underlying mathematical relations for reactor core problems with global reflection and/or rotation symmetry within the context of COMET’s incident flux response expansion theory. The derivation rigorously establishes the relationships between the expansion moments of the incoming and outgoing partial current across coarse mesh surfaces and their corresponding symmetric surfaces under various scenarios in the core. These global (i.e., whole-core) symmetry relations are then integrated into the hybrid stochastic deterministic coarse mesh transport code COMET, enabling the new code to model a portion of reactor cores which have reflection and/or rotation symmetry without increasing the number of unique coarse meshes in the precomputation of the COMET response function library. The new COMET code is numerically validated in Cartesian and Hexagonal geometries by using two sets of problems, namely, a set of stylized PWR benchmark core configuration with 1/8th reflection symmetry and a set of three Advanced High Temperature Reactor (AHTR) core configurations with 120° rotation symmetry. Results from these benchmark calculations demonstrate that the core eigenvalues and fission density distributions predicted by modeling only a portion of the core using the global symmetry relations are in excellent agreement with the full core results as expected. The difference in the core eigenvalues varies from 0 to 2 pcm for both the PWR and AHTR benchmark problems. The average relative differences in the fission density distributions range from 0.012% to 0.014% and from 0.044% to 0.060% for the PWR and AHTR problems, respectively. All the discrepancies fall within three standard deviations of the corresponding COMET uncertainties. Additionally, it is found that modeling just the symmetric portion of the cores speed up COMET by eight and three times for the PWR and AHTR core configurations, respectively.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111639"},"PeriodicalIF":1.9,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144313808","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

Physics Informed Neural Networks for the mixed dual form of the neutron diffusion equation with heterogeneous coefficients 具有非均匀系数的中子扩散方程的混合对偶形式的物理信息神经网络

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-19 DOI: 10.1016/j.anucene.2025.111607

Minh-Hieu Do, Karim Ammar, Nicolas Gerard Castaing, François Madiot

{"title":"Physics Informed Neural Networks for the mixed dual form of the neutron diffusion equation with heterogeneous coefficients","authors":"Minh-Hieu Do, Karim Ammar, Nicolas Gerard Castaing, François Madiot","doi":"10.1016/j.anucene.2025.111607","DOIUrl":"10.1016/j.anucene.2025.111607","url":null,"abstract":"<div><div>Physics-Informed Neural Networks (PINNs), a popular deep learning framework for numerical approximations of Partial Differential Equations (PDEs), are investigated in this work to approximate the solution of the neutron diffusion equation, which is used in simulations of nuclear reactor cores. Moreover, this equation may have low regularity solution due to heterogeneous coefficients, which presents a challenge for the PINNs approach based on the primal form of the neutron diffusion equation. In this work, we study the PINNs approach for the mixed dual form of the neutron diffusion equation and aim to demonstrate that it can significantly improve the accuracy of the approximate solution, especially in cases with heterogeneous coefficients, compared to the primal approach. Besides, neural networks are typically based on the inverse power method for the k-eigenvalue problem, and it is well-known that this algorithm converges very slowly if the dominance ratio is high, as is commonly the case in several reactor physics applications. Therefore, we also discuss some acceleration methods for the PINNs approach applied to the k-eigenvalue problem. Several numerical test cases for the source and k-eigenvalue problems illustrate our purposes.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111607"},"PeriodicalIF":1.9,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144313809","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

CFD analysis on the safety performance of CSNS solid target under a postulated large loss of coolant accident 假设大损失冷却剂事故下CSNS固体靶安全性能CFD分析

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-18 DOI: 10.1016/j.anucene.2025.111654

Zhiyu Yang , Songbai Cheng , Youlian Lu , Songlin Wang , Bin Zhou , Tianjiao Liang , Kai Wang , Jianfei Tong

引用次数: 0

Plate-fin heat exchanger optimal design for industry using both single and multi-objective granularity based surrogate assisted Kho-Kho optimization 基于单目标和多目标粒度的代理辅助Kho-Kho优化的工业板翅式换热器优化设计

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-18 DOI: 10.1016/j.anucene.2025.111605

Subinaya Mohapatra , Dushmanta Kumar Das , Amit Kumar Singh

{"title":"Plate-fin heat exchanger optimal design for industry using both single and multi-objective granularity based surrogate assisted Kho-Kho optimization","authors":"Subinaya Mohapatra , Dushmanta Kumar Das , Amit Kumar Singh","doi":"10.1016/j.anucene.2025.111605","DOIUrl":"10.1016/j.anucene.2025.111605","url":null,"abstract":"<div><div>All engineering devices stand on the basis of design. The mechanical design of Plate-fin heat exchanger (PFHE) always needs a better design to reduce cost while increasing productivity. For an optimal design of PFHE, three distinct issues: total heat transfer area, total volume, and total annual cost, are tackled using a novel meta-heuristic approach. This method is termed as the Granularity-based Surrogate-assisted Kho-Kho (GBSA-KKO) approach. The population is granulated into two subsets, i.e., fine grained and coarse grained and then different approximation methods are implemented with new infill criteria. Eight different benchmark functions are carried out to estimate the efficiency of the proposed GBSA-KKO approach. In conclusion, the proposed optimization approaches successfully minimize the objectives of total heat transfer area, total volume, and total annual cost, yielding values of 79.35 m<span><math><msup><mrow></mrow><mrow><mn>2</mn></mrow></msup></math></span>, 0.00247 m<span><math><msup><mrow></mrow><mrow><mn>3</mn></mrow></msup></math></span>, and 838.218$, respectively.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111605"},"PeriodicalIF":1.9,"publicationDate":"2025-06-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144307011","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 of critical heat flux for upflowed water in narrow rectangular channels with different dimensions 不同尺寸矩形窄通道上升水临界热流密度的实验研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-18 DOI: 10.1016/j.anucene.2025.111668

Yu Zhao , Jianbang Wu , Xingliang Zhang , Wei Zhang , Bo Kuang , Pengfei Liu

{"title":"Experimental study of critical heat flux for upflowed water in narrow rectangular channels with different dimensions","authors":"Yu Zhao , Jianbang Wu , Xingliang Zhang , Wei Zhang , Bo Kuang , Pengfei Liu","doi":"10.1016/j.anucene.2025.111668","DOIUrl":"10.1016/j.anucene.2025.111668","url":null,"abstract":"<div><div>Flow boiling is an efficient heat transfer method; however, critical heat flux (CHF) leads to a sharp deterioration in thermal performance. As a key phenomenon in reactor systems, CHF has garnered significant research attention. To investigate the effects of geometric and thermodynamic parameters on CHF in rectangular narrow channels, an extensive experimental study was conducted across a broad parameter range, including pressures of 0.1–5.5 MPa, mass fluxes of 200–2000 kg/m<sup>2</sup>s, and inlet subcooling levels of 10–150 K. The experimental data were analyzed to elucidate the CHF triggering mechanism and the influence of various parameters. The results demonstrate that pressure, mass flux, inlet subcooling, channel length, and gap size significantly affect CHF. The Look-Up-Table method for CHF prediction was evaluated and found unsuitable for narrow rectangular channels. Comparisons with existing correlations revealed deviations in calculated results, likely due to the limited parameter ranges covered in prior studies. Based on the dimensionless correlation of heat flux and mass flux, a new CHF model was developed, incorporating channel dimension effects. The proposed correlation accurately captures the parametric trends and shows excellent agreement with the experimental data.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111668"},"PeriodicalIF":1.9,"publicationDate":"2025-06-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144313677","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

Disposal of large quantities of plutonium and thorium utilization in VVER-1200 reactors using americium-stabilized MOX fuel 处理使用镅稳定MOX燃料的VVER-1200反应堆中大量钚和钍的利用

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-18 DOI: 10.1016/j.anucene.2025.111670

Ayhan Kara, Emil Mammadzada

引用次数: 0