rdf-syntax-grammar
mods:
  schema location: http://www.loc.gov/mods/v3 http://www.loc.gov/standards/mods/v3/mods-3-2.xsd
  title info:
    title: RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel
  title info:
    title: RELAP[five]/MOD[three point two] analysis of a VVER-[one thousand] reactor with UO[subscript two] fuel and MOX fuel
  name:
    name part: Fu, Chun
    name part: 1970-
    role:
      role term: creator
  type of resource: text
  genre: bibliography
  origin info:
    place:
      place term: xx
    date issued: 2000
    issuance: monographic
  language:
    language term: eng
  physical description:
    form: print
    form: remote
    extent: xi, 64 leaves : illustrations ; 28 cm.
  abstract: A RELAP5/MOD3.2 model of a VVER-1000/MODEL V320 nuclear power plant, Balakovo Unit 4, was updated, improved and validated on the basis of an input deck prepared by the Kurchatov Institute of Moscow. The RELAP5 model includes both the primary and the secondary systems. The Emergency Core Cooling System (ECCS) is modeled according to the plant configuration. The feedwater system, along with the emergency feedwater system, is included in the model. The point reactor kinetics model, in which the decay heat is calculated with ANS decay heat data, enables the model to be used for analysis of a large spectrum of transients and accidents. The plant model is used for analysis and prediction of a cold leg Large Break Loss-of-Coolant Accident (LBLOCA). The RELAP5/MOD3.2 results showed a good agreement with calculations obtained with TECH-M computer program. The cladding temperatures of the MOX assembly have been compared with that of the hot UO₂ assembly. The peak cladding temperature of MOX assembly is about 55 K higher than that of UO₂ assembly. An uncertainty analysis has been performed for the peak cladding temperature, in which Monte Carlo calculations have been performed using the response surface built up from fifteen sets of RELAP5 calculations. The result shows that the ECCS would be sufficient to keep the cladding temperature during the scenario of a LBLOCA well below the required licensing limit.
  note: by Chun Fu.
  note: "Major subject: Nuclear Engineering".
  note: Vita.
  note: Also available online.
  note: Issued also on microfiche from Lange Micrographics.
  note: M.S. Texas A&M University 2000.
  note: Includes bibliographical references (leaves 61-63).
  subject:
    topic: Major nuclear engineering
  identifier: https://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8
  related item:
    location:
      url: https://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8
  record info:
    record content source: TXA
    record creation date: 010405
    record change date: 20220103134807.0
    record identifier: in00001607194