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 [1];  [1];  [1];  [1];  [2]
  1. ORNL
  2. University of Tennessee, Knoxville (UTK)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: M and C 2015, Nashville, TN, USA, 20150419, 20150419
Country of Publication:
United States

Citation Formats

Rearden, Bradley T, Bekar, Kursat B, Celik, Cihangir, Perfetti, Christopher M, and Hart, S. W. D. ADVANCEMENTS IN MONTE CARLO CAPABILITIES FOR SCALE 6.2. United States: N. p., 2015. Web.
Rearden, Bradley T, Bekar, Kursat B, Celik, Cihangir, Perfetti, Christopher M, & Hart, S. W. D. ADVANCEMENTS IN MONTE CARLO CAPABILITIES FOR SCALE 6.2. United States.
Rearden, Bradley T, Bekar, Kursat B, Celik, Cihangir, Perfetti, Christopher M, and Hart, S. W. D. 2015. "ADVANCEMENTS IN MONTE CARLO CAPABILITIES FOR SCALE 6.2". United States. doi:.
author = {Rearden, Bradley T and Bekar, Kursat B and Celik, Cihangir and Perfetti, Christopher M and Hart, S. W. D.},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2015,
month = 1

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  • SCALE code system is developed and maintained by Oak Ridge National Laboratory to perform criticality safety, reactor analysis, radiation shielding, and spent fuel characterization for nuclear facilities and transportation/storage package designs. SCALE is a modular code system that includes several codes which use either Monte Carlo or discrete ordinates solution methodologies for solving relevant neutral particle transport equations. This paper describes some of the key capabilities of the Monte Carlo criticality safety codes within the SCALE code system.
  • Monte Carlo tools in SCALE are commonly used in criticality safety calculations as well as sensitivity and uncertainty analysis, depletion, and criticality alarm system analyses. Recent improvements in the continuous-energy data generated by the AMPX code system and significant advancements in the continuous-energy treatment in the KENO Monte Carlo eigenvalue codes facilitate the use of SCALE Monte Carlo codes to model geometrically complex systems with enhanced solution fidelity. The addition of continuous-energy treatment to the SCALE Monaco code, which can be used with automatic variance reduction in the hybrid MAVRIC sequence, provides significant enhancements, especially for criticality alarm system modeling.more » This paper describes some of the advancements in continuous-energy Monte Carlo codes within the SCALE code system.« less
  • SCALE is a widely used suite of tools for nuclear systems modeling and simulation that provides comprehensive, verified and validated, user-friendly capabilities for criticality safety, reactor physics, radiation shielding, and sensitivity and uncertainty analysis. For more than 30 years, regulators, industry, and research institutions around the world have used SCALE for nuclear safety analysis and design. SCALE provides a plug-and-play framework that includes three deterministic and three Monte Carlo radiation transport solvers that are selected based on the desired solution. SCALE includes the latest nuclear data libraries for continuous-energy and multigroup radiation transport as well as activation, depletion, and decaymore » calculations. SCALE s graphical user interfaces assist with accurate system modeling, visualization, and convenient access to desired results. SCALE 6.2 provides several new capabilities and significant improvements in many existing features, especially with expanded continuous-energy Monte Carlo capabilities for criticality safety, shielding, depletion, sensitivity and uncertainty analysis, and improved fidelity in nuclear data libraries. A brief overview of SCALE capabilities is provided with emphasis on new features for SCALE 6.2.« less
  • Milagro is a stand-alone, radiation-only, code that performs nonlinear radiative transfer calculations using the Fleck and Cummings method of Implicit Monte Carlo (IMC). Milagro is an object-oriented, C++ code that utilizes classes in our group's (CCS-4) radiation transport library. Milagro and its underlying classes have been significantly upgraded since 1998, when results from Milagro were first presented. Most notably, the object-oriented design has been revised to allow for optimal stand-alone parallel efficiency and rapid integration of new classes. For example, the better design, coupled with stringent component testing, allowed for immediate integration of the full domain decomposition parallel scheme. (Itmore » is a simple philosophy: spend time on the design, and debug early and once.) Milagro's classes are templated on mesh type. Currently, it runs on an orthogonal, structured, not-necessarily-uniform, Cartesian mesh of up to three dimensions, an RZ-Wedge mesh, and soon a tetrahedral mesh. Milagro considers one-frequency, or ''grey,'' radiation with isotropic scattering, user-defined analytic opacities and equation-of-state, and various source types: surface, material, and radiation. Tallies produced by Milagro include energy and momentum deposition. In parallel, Milagro can run on a mesh that is fully replicated on all processors or on a mesh that is fully decomposed in the spatial domain. Milagro is reproducible, regardless of number of processors or parallel topology, and it now exactly conserves energy both globally and locally. Milagro has the capability for EnSight graphics and restarting. Finally, Milagro has been well verified with its use of Design-by-Contract{trademark}, component tests, and regression tests, and with its agreement to results of analytic test problems. By successfully running analytic and benchmark problems, Milagro serves to integrally verify all of its underlying classes, thus paving the way for other service packages based on these classes.« less