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Pedigree Analysis of the MELCOR 1.8.2 Code to be Used for ITER'S Report Preliminary on Safety.


DE2007912912

Publication Date 2007
Personal Author Moore, R. L.
Page Count 60
Abstract This report documents the pedigree analysis of the MELCOR 1.8.2 code to be used for ITERs Report Preliminary on Safety. To pedigree the code the process involved four steps. The first step was taking the modified MELCOR 1.8.2 code used by the ITER Joint Central Team (JCT) for analyses in previous ITER Safety Assessments and comparing the FORTRAN code of this version line-by-line to the original 1.8.2 version of MELCOR. The second step was a nonregression analysis which involves comparing the results from the pedigreed version against those predicted by the original, unmodified version of MELCOR 1.8.2. The third step involved comparing the pedigreed version results to results from the MELCOR version used by the ITER JCT for the Generic Site Safety Report (GSSR) against a set of accident problems analyzed for the safety report. The fourth and final step involved a comparison between the pedigreed version of the code and the developmental test problems cited in the change documents referenced in this report. The results from the pedigree process are described in this report.
Keywords
  • Nuclear power plants
  • Reactor safety
  • Computer codes
  • Hydraulics
  • Reactor cooling systems
  • Thermal analysis
  • Reactor accidents
  • Engineering safety systems
  • MELCOR computer code
  • Light water reactors
Source Agency
  • Technical Information Center Oak Ridge Tennessee
Corporate Authors Idaho National Engineering Lab., Idaho Falls.; Department of Energy, Washington, DC. Office of Nuclear Energy Programs.
Supplemental Notes Sponsored by Department of Energy, Washington, DC. Office of Nuclear Energy Programs.
Document Type Technical Report
NTIS Issue Number 200726
Pedigree Analysis of the MELCOR 1.8.2 Code to be Used for ITER'S Report Preliminary on Safety.
Pedigree Analysis of the MELCOR 1.8.2 Code to be Used for ITER'S Report Preliminary on Safety.
DE2007912912

  • Nuclear power plants
  • Reactor safety
  • Computer codes
  • Hydraulics
  • Reactor cooling systems
  • Thermal analysis
  • Reactor accidents
  • Engineering safety systems
  • MELCOR computer code
  • Light water reactors
  • Technical Information Center Oak Ridge Tennessee
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