{"title":"CFD simulation of internal center flow blockage in helical-cruciform fuel assembly","authors":"Z.S. Li , C. Hu , B.H. Yan , L.S. Wang","doi":"10.1016/j.pnucene.2025.105831","DOIUrl":null,"url":null,"abstract":"<div><div>Helical-cruciform fuel (HCF) rod, an innovative fuel design, has been proposed for its promising thermal-hydraulic performances, which is characterized by contacting at points between rods to achieve self-supporting without space grids. Blockages are most likely to occur at contact point zone for the deteriorated fluidity and a flow blockage accident is caused. Hence, flow characterization of coolant flow in 7 rods HCF assembly with internal center blockage has been carried out by Reynolds-Averaged Navier-Stokes (RANS) based CFD simulation. In this paper, influence of different minimum gap values between petals have been evaluated. Based on this, different turbulence models have been validated for the law of the wall, after which CFD results of axial velocity profiles in the interior and exterior channel have been compared against in-house hydraulic experimental data of 7 HCF rod bundle. Focus has been paid to analyzing hydraulic features in HCF assembly with various blockage configurations, including different thicknesses and blocked percentage of flow channel sectional area. It is observed that special vortex structure formed upstream and downstream in typical blockage conditions. The transverse flow upstream and downstream of blockages is enhanced with increasing blockage thickness and blocked area. The results of the present study would serve as foundation for further in-depth flow blockage incidents analyses in HCF rod assembly.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"186 ","pages":"Article 105831"},"PeriodicalIF":3.3000,"publicationDate":"2025-05-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S014919702500229X","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
Helical-cruciform fuel (HCF) rod, an innovative fuel design, has been proposed for its promising thermal-hydraulic performances, which is characterized by contacting at points between rods to achieve self-supporting without space grids. Blockages are most likely to occur at contact point zone for the deteriorated fluidity and a flow blockage accident is caused. Hence, flow characterization of coolant flow in 7 rods HCF assembly with internal center blockage has been carried out by Reynolds-Averaged Navier-Stokes (RANS) based CFD simulation. In this paper, influence of different minimum gap values between petals have been evaluated. Based on this, different turbulence models have been validated for the law of the wall, after which CFD results of axial velocity profiles in the interior and exterior channel have been compared against in-house hydraulic experimental data of 7 HCF rod bundle. Focus has been paid to analyzing hydraulic features in HCF assembly with various blockage configurations, including different thicknesses and blocked percentage of flow channel sectional area. It is observed that special vortex structure formed upstream and downstream in typical blockage conditions. The transverse flow upstream and downstream of blockages is enhanced with increasing blockage thickness and blocked area. The results of the present study would serve as foundation for further in-depth flow blockage incidents analyses in HCF rod assembly.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.