Xuesong Li, Meng Zhang, Yang Gao, Hongguo Hou, Caishan Jiao, Nan Chao
{"title":"Coupled heat and mass transfer simulation of CRUD migration and deposition in PWR systems","authors":"Xuesong Li, Meng Zhang, Yang Gao, Hongguo Hou, Caishan Jiao, Nan Chao","doi":"10.1016/j.net.2024.09.016","DOIUrl":null,"url":null,"abstract":"<div><div>In Pressurized Water Reactors (PWRs), corrosion products are released during operation due to the large contact area between the primary circuit coolant and the equipment materials. In this study, a multiphysics model was developed and validated to simulate and analyze the migration and deposition behavior of corrosion products in the primary circuit. The model is useful for calculating the effect of operating conditions on migration and deposition. The effects of mass transfer and subcooled boiling on deposition and re-release were included in the model. Diffusion, convective mass transfer, and transition between ions and particles in the coolant were also considered in the model.</div><div>The model's accuracy was validated by comparison with actual measured data from the Callaway reactor. Calculations showed that the deposition on the steam generator exceeded that on other equipment, primarily attributable to its larger surface area. Additionally, variations in the coolant flow significantly influence the deposition resulting from subcooled boiling, with an increase in flow leading to a noticeable reduction in boiling deposition.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103213"},"PeriodicalIF":2.6000,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S1738573324004625","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
In Pressurized Water Reactors (PWRs), corrosion products are released during operation due to the large contact area between the primary circuit coolant and the equipment materials. In this study, a multiphysics model was developed and validated to simulate and analyze the migration and deposition behavior of corrosion products in the primary circuit. The model is useful for calculating the effect of operating conditions on migration and deposition. The effects of mass transfer and subcooled boiling on deposition and re-release were included in the model. Diffusion, convective mass transfer, and transition between ions and particles in the coolant were also considered in the model.
The model's accuracy was validated by comparison with actual measured data from the Callaway reactor. Calculations showed that the deposition on the steam generator exceeded that on other equipment, primarily attributable to its larger surface area. Additionally, variations in the coolant flow significantly influence the deposition resulting from subcooled boiling, with an increase in flow leading to a noticeable reduction in boiling deposition.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development