Annals of Nuclear Energy最新文献_第5页

A MOC-based heterogeneous leakage model 基于模型模型的异构泄漏模型

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-05-01 DOI: 10.1016/j.anucene.2025.111449

S. Santandrea , L. Graziano

{"title":"A MOC-based heterogeneous leakage model","authors":"S. Santandrea , L. Graziano","doi":"10.1016/j.anucene.2025.111449","DOIUrl":"10.1016/j.anucene.2025.111449","url":null,"abstract":"<div><div>This paper presents some developments of the APOLLO3<span><math><msup><mrow></mrow><mrow><mtext>®</mtext></mrow></msup></math></span>code and their applications in support to industrial studies. We describe a numerical technique to implement, in the framework of the Method Of Characteristics (MOC), the Heterogeneous Leakage Model (HLM). We preliminarily set up the theoretical framework of this model and clarify some aspects related to its use as homogenization technique that we believe important. In fact in the classic use of HLM for homogenization some important approximations are made to switch from complex-valued fluxes to real-valued weighting functions. We suggest an approach to avoid such approximations in practice. Then we describe a new numerical technique to solve with the MOC the HLM. The approach consists in integrating the complex-valued leakage term of the HLM directly in the cross section, and therefore to generalize MOC by integrating a complex-valued function. Moreover we detail also the necessary modifications that are necessary to adapt the classical algorithm of critical search (valid for the classical <span><math><mrow><mi>D</mi><msup><mrow><mi>B</mi></mrow><mrow><mn>2</mn></mrow></msup></mrow></math></span> leakage model) to the new context. Numerical results are shown in support to these developments.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111449"},"PeriodicalIF":1.9,"publicationDate":"2025-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143895777","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

Effect of surface oxidation on minimum film boiling temperature during Zr-4 quenching process Zr-4淬火过程中表面氧化对最低膜沸腾温度的影响

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-30 DOI: 10.1016/j.anucene.2025.111516

Lei Zhong , Zefeng Wang , Hongxing Yu , Jian Deng , Chen Ling , Dongyong Wang

{"title":"Effect of surface oxidation on minimum film boiling temperature during Zr-4 quenching process","authors":"Lei Zhong , Zefeng Wang , Hongxing Yu , Jian Deng , Chen Ling , Dongyong Wang","doi":"10.1016/j.anucene.2025.111516","DOIUrl":"10.1016/j.anucene.2025.111516","url":null,"abstract":"<div><div>The minimum film boiling temperature is the impassable temperature point in the quenching transient, which indicates whether the fuel cladding surface is cooled effectively. Based on the Rayley-Taylor instability theory, this paper considers the influence of vapor–liquid interface fluctuation on the collapse of the vapor film during film boiling. The evaporation angle is introduced to quantify the intensity of vapor–liquid interface fluctuation, and the evaporation angle is connected with the wall hydrophilicity. The evaporation angle near the quench front is measured through the visual quenching experiment, and the contact angle of the Zr-4 surface is measured through the liquid drop experiment. The relationship between the evaperation angle of the vapor–liquid interface and the contact angle of the wall surface is obtained. The results show that surface oxidation can reduce the surface contact angle of Zr-4 alloy, which makes the vapor–liquid interface fluctuate more violently during quenching, and thus reduces the minimum film boiling temperature.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111516"},"PeriodicalIF":1.9,"publicationDate":"2025-04-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143887698","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

Preliminary development and validation of the thermal–hydraulic module for ADS system analysis code 初步开发并验证了用于ADS系统的热液模块分析代码

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-29 DOI: 10.1016/j.anucene.2025.111515

Yanling Zhu , Peng Fang , Feng Zhou , Qiuying Liang , Shijie Du , Yongwei Yang , Lei Yang

{"title":"Preliminary development and validation of the thermal–hydraulic module for ADS system analysis code","authors":"Yanling Zhu , Peng Fang , Feng Zhou , Qiuying Liang , Shijie Du , Yongwei Yang , Lei Yang","doi":"10.1016/j.anucene.2025.111515","DOIUrl":"10.1016/j.anucene.2025.111515","url":null,"abstract":"<div><div>To address the design and safety analysis requirements of China initiative Accelerator Driven System (CiADS), it is essential to develop a specialized system analysis code with independent intellectual property rights. Given the subcritical operation characteristics of the Accelerator Driven Subcritical System (ADS), this paper aims to preliminarily develop and validate the thermal–hydraulic module of the ADS system analysis code, facilitating comprehensive and flexible modeling of the primary thermal–hydraulic system through fluid network technology. To effectively solve the computational model, appropriate numerical methods were selected based on the specific characteristics of each individual model. Preliminary validation was conducted using the Experimental Breeder Reactor II (EBR-II) benchmark, including both protected and unprotected loss-of-flow transients, SHRT-17 and SHRT-45R. The results demonstrated reasonable agreement between the calculated and experimental values in terms of magnitude and trends, confirming the accuracy of the computational model. It is preliminary indicated that the code possesses the capability for transient thermal–hydraulic and safety analysis of the primary system, laying a solid foundation for the future development of a more comprehensive ADS system analysis code.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111515"},"PeriodicalIF":1.9,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143882504","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

Predicting critical heat flux with uncertainty quantification and domain generalization using conditional variational autoencoders and deep neural networks 基于条件变分自编码器和深度神经网络的不确定性量化和领域泛化预测临界热流

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-28 DOI: 10.1016/j.anucene.2025.111502

Farah Alsafadi, Aidan Furlong, Xu Wu

引用次数: 0

Method research on equilibrium cycle reloading pattern optimization for the HPR1000 reactor core using deep learning-enhanced multi-objective genetic algorithm 基于深度学习增强多目标遗传算法的HPR1000堆芯平衡循环重装模式优化方法研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-28 DOI: 10.1016/j.anucene.2025.111456

Muhammad Kamran Butt , Chenghui Wan , Luo Wei , Izat Khan , Liangzhi Cao

引用次数: 0

Development of a two-phase flow solver with two-fluid model based on OpenFOAM: Validation against two-phase boiling flow 基于OpenFOAM的双流体模型两相流求解器的开发：对两相沸腾流的验证

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-25 DOI: 10.1016/j.anucene.2025.111491

Wenqiang Wu , Tao Huang , Peng Du , Zhenyu Feng , Dalin Zhang , Lei Zhou , Gongle Song , Jian Deng , Zhifang Qiu , Wenxi Tian , Suizheng Qiu , Guanghui Su

{"title":"Development of a two-phase flow solver with two-fluid model based on OpenFOAM: Validation against two-phase boiling flow","authors":"Wenqiang Wu , Tao Huang , Peng Du , Zhenyu Feng , Dalin Zhang , Lei Zhou , Gongle Song , Jian Deng , Zhifang Qiu , Wenxi Tian , Suizheng Qiu , Guanghui Su","doi":"10.1016/j.anucene.2025.111491","DOIUrl":"10.1016/j.anucene.2025.111491","url":null,"abstract":"<div><div>The continuous advancement in computer technology and mathematical-physical models has significantly propelled the development of numerical reactor technology. There is a growing focus on high-fidelity, multi-scale, and multi-physics coupling within a unified framework. OpenFOAM, based on the finite volume method, has emerged as a promising tool for addressing this challenge. This study explores its capabilities in system-level scales, successfully developing a two-fluid, six-equation solver. The realistic closure models cover flow and heat transfer scenarios within vertical channels under pre-CHF conditions. A virtual thermal structure accounts for conjugate heat transfer between the fluid and the solid. Furthermore, the solver adheres to the discretization and solution principles within the OpenFOAM framework. The developed solver has been extensively validated against experimental data for two-phase boiling flow, with results showing good agreement, thereby demonstrating the solver’s success. This work builds upon previous efforts involving the drift-flux solver and indicates that OpenFOAM can effectively handle one-dimensional or system-level scale calculations. It provides robust support for future endeavors in multi-scale and multi-physics coupling technologies.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111491"},"PeriodicalIF":1.9,"publicationDate":"2025-04-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868606","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 review of research on melt and coolant interaction under different injection modes 不同喷射方式下熔体与冷却剂相互作用研究综述

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-25 DOI: 10.1016/j.anucene.2025.111495

Wenshu Jiang, Shuhua Zhou, Shuo Wang, Ruizhi Hao, Tao Lu

{"title":"A review of research on melt and coolant interaction under different injection modes","authors":"Wenshu Jiang, Shuhua Zhou, Shuo Wang, Ruizhi Hao, Tao Lu","doi":"10.1016/j.anucene.2025.111495","DOIUrl":"10.1016/j.anucene.2025.111495","url":null,"abstract":"<div><div>The interaction of high-temperature melt with coolant, also known as fuel–coolant interaction (FCI) or coolant-coolant interaction (CCI), should be considered one of the crucial factors causing devastation in nuclear reactor accidents. Based on different accident scenarios, the interaction modes between melt and coolant can be categorized into the melt-injection (MI) mode and the coolant-injection (CI) mode. In previous research, performing visualization experiments of the CI mode was challenging due to the opacity of metals. Considering that the CI mode is geometrically opposite to the MI mode, it is promising to obtain the fundamental interaction mechanisms of the CI mode from the research on the MI mode. Therefore, this review systematically summarizes the essential theories, prevailing experiments, and simulations of melt-coolant interaction according to the different interaction modes, focusing on the thermodynamic and hydrodynamic interaction processes, as well as current hotspots and challenges. Its core significance is to analyze melt-coolant interaction from the opposite processes of the CI mode and the MI mode, which could provide a new perspective for the research of the CI mode. Meanwhile, this review offers valuable insights for the subsequent research directions of melt-coolant interaction, such as optimizing empirical parameters in existing theoretical models and developing corresponding interfacial heat transfer model and the thermal expansion model of vapor explosions, which is crucial for predicting the potential risk of nuclear reactor accidents.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111495"},"PeriodicalIF":1.9,"publicationDate":"2025-04-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143874171","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

Development and benchmarking of a point detector in OpenMC OpenMC中一个点检测器的开发和基准测试

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-25 DOI: 10.1016/j.anucene.2025.111497

Itay Horin , Or Alon , Arik Kreisel , Tsviki Y. Hirsh , Tamar Dayan , Hallel Fuks

引用次数: 0

Development of a new onset of film boiling model within the fouling layer 建立了一种新的污染层内膜沸腾开始模型

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-25 DOI: 10.1016/j.anucene.2025.111488

Xiaowen Wang , Maolong Liu , Rui Zhang , Tenglong Cong , Yao Xiao , Hanyang Gu

引用次数: 0

Radioisotope production at the advanced test reactor: process and lessons learned 先进试验反应堆的放射性同位素生产：过程和经验教训

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-24 DOI: 10.1016/j.anucene.2025.111463

Andrew Zillmer, Clinton Wilson, Jill Mitchell, Austen Fradeneck, Ryan Marlow, Erik Rosvall, William Green, Justin Lower

引用次数: 0