Skip to main navigation Skip to search Skip to main content

Study of the nuclear fuel behavior with coupled three-dimensional neutronics/thermal-hydraulic codes

  • C. Parisi
  • , K. N. Ivanov
  • , F. D'Auria

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

Fuel behavior of a WWER-1000 reactor during a Rod Ejection Accident (REA) is studied in this paper. Tools used are a coupled three-dimensional (3D) neutronics / thermal-hydraulic codes for the study of the transient and a 2D neutronics transport code for the generation of the cross sections libraries. Sensitivity analyses were performed varying various physical parameters. The effect of different cross section modelling and the effect of various states of operation of the plant on the transient evolution were also investigated.

Original languageEnglish
Title of host publicationProceedings of the PHYSOR 2004
Subtitle of host publicationThe Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Pages2009-2013
Number of pages5
StatePublished - 2004
Externally publishedYes
EventPHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments - Chicago, IL, United States
Duration: Apr 25 2004Apr 29 2004

Publication series

NameProceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

Conference

ConferencePHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Country/TerritoryUnited States
CityChicago, IL
Period04/25/0404/29/04

Keywords

  • Coupled Codes
  • Cross Section Generation
  • Energy Release to the Fuel
  • Nuclear Fuel Behavior
  • Rod Ejection Accident

Fingerprint

Dive into the research topics of 'Study of the nuclear fuel behavior with coupled three-dimensional neutronics/thermal-hydraulic codes'. Together they form a unique fingerprint.

Cite this