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Title: The New MCNP6 Depletion Capability

The first MCNP based inline Monte Carlo depletion capability was officially released from the Radiation Safety Information and Computational Center as MCNPX 2.6.0. Both the MCNP5 and MCNPX codes have historically provided a successful combinatorial geometry based, continuous energy, Monte Carlo radiation transport solution for advanced reactor modeling and simulation. However, due to separate development pathways, useful simulation capabilities were dispersed between both codes and not unified in a single technology. MCNP6, the next evolution in the MCNP suite of codes, now combines the capability of both simulation tools, as well as providing new advanced technology, in a single radiation transport code. We describe here the new capabilities of the MCNP6 depletion code dating from the official RSICC release MCNPX 2.6.0, reported previously, to the now current state of MCNP6. NEA/OECD benchmark results are also reported. The MCNP6 depletion capability enhancements beyond MCNPX 2.6.0 reported here include: (1) new performance enhancing parallel architecture that implements both shared and distributed memory constructs; (2) enhanced memory management that maximizes calculation fidelity; and (3) improved burnup physics for better nuclide prediction. MCNP6 depletion enables complete, relatively easy-to-use depletion calculations in a single Monte Carlo code. The enhancements described here help provide a powerfulmore » capability as well as dictate a path forward for future development to improve the usefulness of the technology.« less
Authors:
 [1] ;  [1] ;  [1] ;  [1]
  1. Los Alamos National Laboratory
Publication Date:
OSTI Identifier:
1044109
Report Number(s):
LA-UR-12-22314
TRN: US1203332
DOE Contract Number:
AC52-06NA25396
Resource Type:
Conference
Resource Relation:
Conference: International Congress on the Advances in Nuclear Power Plants ; 2012-06-24 - 2012-06-28 ; Chicago, Illinois, United States
Research Org:
Los Alamos National Laboratory (LANL)
Sponsoring Org:
DOE/LANL
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; AGE ESTIMATION; ARCHITECTURE; BENCHMARKS; BURNUP; FORECASTING; GEOMETRY; ISOTOPES; MEMORY MANAGEMENT; NUCLEAR POWER PLANTS; PERFORMANCE; PHYSICS; RADIATION PROTECTION; RADIATION TRANSPORT; SIMULATION