3D digital simulation technology for design and optimization of nuclear pressure vessel

3D digital simulation technology for design and optimization of nuclear pressure vessel | Research Square window.SnipcartSettings = { analytics: { enabled: false } }; (function() { var accessVector = localStorage.getItem('access_vector') || ''; window.dataLayer = window.dataLayer || []; if (accessVector) { window.dataLayer.push({ user: { profile: { profileInfo: { snid: accessVector } } } }); } })(); (function(w,d,s,l,i){w[l]=w[l]||[];w[l].push({'gtm.start':new Date().getTime(),event:'gtm.js'});var f=d.getElementsByTagName(s)[0],j=d.createElement(s),dl=l!='dataLayer'?'&l='+l:'';j.async=true;j.src='https://www.googletagmanager.com/gtm.js?id='+i+dl;f.parentNode.insertBefore(j,f);})(window,document,'script','dataLayer','GTM-K279D39R'); Browse Preprints In Review Journals COVID-19 Preprints AJE Video Bytes Research Tools Research Promotion AJE Professional Editing AJE Rubriq About Preprint Platform In Review Editorial Policies Our Team Advisory Board Help Center Sign In Submit a Preprint Cite Share Download PDF Research Article 3D digital simulation technology for design and optimization of nuclear pressure vessel Yuejuan WANG, Qingfeng Wang, Chengcheng Zhang This is a preprint; it has not been peer reviewed by a journal. https://doi.org/ 10.21203/rs.3.rs-8656713/v1 This work is licensed under a CC BY 4.0 License Status: Under Review Version 1 posted 5 You are reading this latest preprint version Abstract This paper focuses on the 3D digital simulation technology for design and optimization of Pakistan Spherical Tokamak (PST) pressure vessel. The PST is a lower aspect ratio tokamak that aims to do research on the nuclear fusion science and technology. The PST pressure vessel, as a nuclear pressure vessel, is one of the key components of fusion reactor. This study using CATIA for pressure vessel structural design, while utilizing ANSYS for pressure vessel structural parameter optimization analysis. The electromagnetic-thermal-mechanical coupling effect research is systematically addressed to improve safety margins while ensuring plasma operation stability. The research results of this article can provide theoretical and engineering references for the commercialization of compact fusion reactors in the future. Nuclear pressure vessel 3D digital simulation CATIA ANSYS Full Text Additional Declarations No competing interests reported. Cite Share Download PDF Status: Under Review Version 1 posted Reviewers agreed at journal 12 May, 2026 Reviewers invited by journal 07 May, 2026 Editor assigned by journal 22 Jan, 2026 Submission checks completed at journal 21 Jan, 2026 First submitted to journal 21 Jan, 2026 You are reading this latest preprint version Research Square lets you share your work early, gain feedback from the community, and start making changes to your manuscript prior to peer review in a journal. As a division of Research Square Company, we’re committed to making research communication faster, fairer, and more useful. We do this by developing innovative software and high quality services for the global research community. Our growing team is made up of researchers and industry professionals working together to solve the most critical problems facing scientific publishing. Also discoverable on Platform About Our Team In Review Editorial Policies Advisory Board Help Center Resources Author Services Accessibility API Access RSS feed Manage Cookie Preferences © Research Square 2026 | ISSN 2693-5015 (online) Privacy Policy Terms of Service Do Not Sell My Personal Information {"props":{"pageProps":{"initialData":{"identity":"rs-8656713","acceptedTermsAndConditions":true,"allowDirectSubmit":false,"archivedVersions":[],"articleType":"Research Article","associatedPublications":[],"authors":[{"id":641647235,"identity":"8a4e0be4-1d6b-482e-b4d3-bf3a769aba02","order_by":0,"name":"Yuejuan WANG","email":"","orcid":"","institution":"Anhui Technical College of Industry and Economy","correspondingAuthor":false,"prefix":"","firstName":"Yuejuan","middleName":"","lastName":"WANG","suffix":""},{"id":641647238,"identity":"a4113a18-03c8-4d56-8f4c-da16e280afc4","order_by":1,"name":"Qingfeng Wang","email":"data:image/png;base64,iVBORw0KGgoAAAANSUhEUgAAAZAAAAAyAQMAAABI0h/eAAAABlBMVEX///8AAABVwtN+AAAACXBIWXMAAA7EAAAOxAGVKw4bAAAAxElEQVRIiWNgGAWjYBAC9gYILcdGtBaeAxDamHQtiQ3Ea2HvPfyCoexwep907wGGHzUM8uYEtfCcS7NgOHc4t03mXAJjzzEGw52E7LOXyDEzYGy7ndsmkWPAwNvAkGBwgJAt8m/AWtLZgFoY/xKlRYLH+AFQSwJICzNxtvDkmDEknPtvCPLLYZljEoYbCGphP2P84UNZmrz87N6DD9/U2MgTtAUI2CQSQPEowcMAVCxBWD0QMH9ggGoZBaNgFIyCUYAVAABqijoAWzn0KAAAAABJRU5ErkJggg==","orcid":"","institution":"Chinese Academy of Sciences","correspondingAuthor":true,"prefix":"","firstName":"Qingfeng","middleName":"","lastName":"Wang","suffix":""},{"id":641647239,"identity":"005b6c30-fbe9-4102-b4b7-30cae6162946","order_by":2,"name":"Chengcheng Zhang","email":"","orcid":"","institution":"Chinese Academy of Sciences","correspondingAuthor":false,"prefix":"","firstName":"Chengcheng","middleName":"","lastName":"Zhang","suffix":""}],"badges":[],"createdAt":"2026-01-21 07:51:45","currentVersionCode":1,"declarations":"","doi":"10.21203/rs.3.rs-8656713/v1","doiUrl":"https://doi.org/10.21203/rs.3.rs-8656713/v1","draftVersion":[],"editorialEvents":[],"editorialNote":"","failedWorkflow":false,"files":[{"id":109438417,"identity":"f22d0a5b-23ca-4ccc-b17a-b1f29fb5c5d5","added_by":"auto","created_at":"2026-05-18 06:41:35","extension":"pdf","order_by":1,"title":"","display":"","copyAsset":false,"role":"manuscript-pdf","size":564232,"visible":true,"origin":"","legend":"","description":"","filename":"Manuscript3DdigitalsimulationtechnologyfordesignandoptimizationofnuclearpressurevesselV1.0.pdf","url":"https://assets-eu.researchsquare.com/files/rs-8656713/v1_covered_0bb56f3e-5fd2-4ec5-b613-faa9afa602b4.pdf"}],"financialInterests":"No competing interests reported.","formattedTitle":"3D digital simulation technology for design and optimization of nuclear pressure vessel","fulltext":[],"fulltextSource":"","fullText":"","funders":[],"hasAdminPriorityOnWorkflow":false,"hasManuscriptDocX":false,"hasOptedInToPreprint":true,"hasPassedJournalQc":"","hasAnyPriority":false,"hideJournal":false,"highlight":"","institution":"","isAcceptedByJournal":false,"isAuthorSuppliedPdf":true,"isDeskRejected":"","isHiddenFromSearch":false,"isInQc":false,"isInWorkflow":false,"isPdf":true,"isPdfUpToDate":true,"isWithdrawnOrRetracted":false,"journal":{"display":true,"email":"[email protected]","identity":"journal-of-fusion-energy","isNatureJournal":false,"hasQc":true,"allowDirectSubmit":false,"externalIdentity":"jofe","sideBox":"Learn more about [Journal of Fusion Energy](http://link.springer.com/journal/10894)","snPcode":"10894","submissionUrl":"https://submission.nature.com/new-submission/10894/3","title":"Journal of Fusion Energy","twitterHandle":"","acdcEnabled":true,"dfaEnabled":true,"editorialSystem":"em","reportingPortfolio":"Springer Hybrid","inReviewEnabled":true,"inReviewRevisionsEnabled":false},"keywords":"Nuclear pressure vessel, 3D digital simulation, CATIA, ANSYS","lastPublishedDoi":"10.21203/rs.3.rs-8656713/v1","lastPublishedDoiUrl":"https://doi.org/10.21203/rs.3.rs-8656713/v1","license":{"name":"CC BY 4.0","url":"https://creativecommons.org/licenses/by/4.0/"},"manuscriptAbstract":"\u003cp\u003eThis paper focuses on the 3D digital simulation technology for design and optimization of Pakistan Spherical Tokamak (PST) pressure vessel. 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