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  • Huang, Zi-NanFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China. (författare)

Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients

  • Artikel/kapitelEngelska2023

Förlag, utgivningsår, omfång ...

  • Elsevier BV,2023
  • printrdacarrier

Nummerbeteckningar

  • LIBRIS-ID:oai:DiVA.org:kth-335986
  • https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-335986URI
  • https://doi.org/10.1016/j.anucene.2023.110067DOI

Kompletterande språkuppgifter

  • Språk:engelska
  • Sammanfattning på:engelska

Ingår i deldatabas

Klassifikation

  • Ämneskategori:ref swepub-contenttype
  • Ämneskategori:art swepub-publicationtype

Anmärkningar

  • QC 20230911
  • The China Initiative Accelerator Driven System (CiADS) was proposed by China Academy of Science since 2015. The subcritical reactor in CiADS is a liquid Lead Bismuth Eutectic (LBE) cooled fast reactor. When the reactor core is in operation, the LBE coolant will directly contact and corrode the inner surface of reactor vessel. Due to the high temperature, the corrosion will be more severe. If the stress on the reactor vessel exceeds the limit, the plastic deformation will occur, leading to the generation and expansion of defects and cracks, and the safety of the reactor will be affected. Therefore, evaluating the stress field of the reactor vessel under different operating conditions is a very important research project. In this paper, the finite element analysis software ADINA was applied to analyze the reactor vessel in CiADS, and the ASME Code was used as stress assessment standards. We can preliminarily prove that the stress assessments of the vessel during the postulated Unprotected Loss of Flow (ULOF) accidents satisfy the requirements of ASME Code. The limit reactivity insertion to protect the vessel from plastic deformation is 0.58$ in the postulated Unprotected Transient over Power (UTOP) accidents based on our current results. Therefore, we can preliminarily conclude that the current material selection and structural design of the reactor vessel in CiADS could survive most of the postulated transient accidents considering the stress effect.

Ämnesord och genrebeteckningar

Biuppslag (personer, institutioner, konferenser, titlar ...)

  • Li, Yun-XiangFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China. (författare)
  • Li, SongFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China. (författare)
  • Xi, BinFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China. (författare)
  • Zhang, You-PengFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China. (författare)
  • Meng, LuFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China. (författare)
  • Wanga, Di-SiFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China. (författare)
  • Liu, BoFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China. (författare)
  • Gu, LongFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China.;Lanzhou Univ, Inst Nucl Sci & Technol, Lanzhou 730000, Peoples R China.;Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China. (författare)
  • Peng, Tian-JiFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China.;Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China. (författare)
  • Zhang, LuFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China.;Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China. (författare)
  • Jiang, WeiFudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China.;Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China. (författare)
  • Wallenius, Janne,1968-KTH,Kärnenergiteknik(Swepub:kth)u1n5mh86 (författare)
  • Fudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China.Fudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China.;Lanzhou Univ, Inst Nucl Sci & Technol, Lanzhou 730000, Peoples R China.;Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China. (creator_code:org_t)

Sammanhörande titlar

  • Ingår i:Annals of Nuclear Energy: Elsevier BV1940306-45491873-2100

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