Published 2013 | Version v1
Miscellaneous Open

Evaluation of Sodium-cooled Fast Reactor Neutronic Benchmarks

  • 1. Argonne National Laboratory, Nuclear Engineering Division (United States)
  • 2. CEA, DEN, DER, Cadarache, F-13108 Saint Paul lez Durance (France)
  • 3. OECD/NEA (France)

Description

Summary of the results obtained between ANL and CEA to model various SFR cores in the frame of the WPRS benchmark: ANL used MC2-3/REBUS-3 system with ENDF/B-VII.0 library; CEA and ANL used the ERANOS system with JEFF3.1 and ENDF/B-VII.0 libraries; MCNP was used at ANL for BOC benchmark with JEFF3.1 and ENDF/B-VII.0 libraries. Furthermore a large difference was observed for K-effective between JEFF3.1 and ENDF/B-VII.0 (main responsible: Pu-238, Pu-239, Pu-240, Na-23; some other isotopes like U-238, Fe-56, O-16 might also have a large impact; the smaller reactivity change (JEFF3.1 → ENDF/B-VII.0), for MOX-3600 with respect to MET-1000, is due to the error cancelation and not to a better agreement between the two libraries

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Part of:
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). Presentations

Additional details

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
Imprint Title
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). Presentations
Imprint Pagination
vp.
Journal Page Range
28 p.
Report number
IAEA-CN--199

Conference

Title
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios
Acronym
FR13
Dates
4-7 Mar 2013
Place
Paris (France)

Optional Information

Notes
PowerPoint presentation
Secondary number(s)
IAEA-CN--199/254