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SUMMARY:"Personal experience in simulation of neutronic transport with sta
 te-of-the-art MCNPX code"
DTSTART:20140321T103000
DTEND:20140321T113000
DTSTAMP:20260919T194533Z
UID:355e325c93409b966c62a84720042bcc74741584865047bc58f59427
CATEGORIES:Conferences - Seminars
DESCRIPTION:Antoine Dupré\, Etudiant EPFL\nIn the frame of my master thes
 is\, I am collaborating with the STARS group at PSI (Switzerland) to asses
 s the fluence of fast neutrons at the reactor pressure vessel of a nuclear
  reactor using widely used probabilistic transport code MCNPX. The work is
  of relevance to obtain precise data and assist the material scientists in
  safety studies.\nAt SCK◦CEN (Belgium)\, I have implemented an algorithm
  for Global Variance Reduction with MCNPX on the basis of a preliminary st
 udy of simplified methodology. The outcome is a script that processes the 
 algorithm and communicates with MCNPX (which source code is not available)
 .\nI will emphasize the major points that drew my interest in these topics
 .
LOCATION:PPB 019
STATUS:CONFIRMED
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