Monaco keno energy
4.1. MAVRIC: Monaco with Automated Variance
The forward Monte Carlo transport is performed using Monaco, a fixed-source shielding code that uses the SCALE General Geometry Package (SGGP, the same as used by the criticality code KENO-VI) and the standard SCALE
Nuclear Energy Agency (NEA)
KENO-VI is a 3D eigenvalue Monte Carlo code for criticality safety and Monaco is a 3D fixed-source Monte Carlo code for shielding analysis. Both codes use the SCALE Standard Composition Library and the SCALE Generalised Geometry Package (SGGP), which allows for versatile modeling of complex geometries and provides convenient, efficient
Shielding Capabilities in SCALE 6.2 Monaco/MAVRIC
Monaco/MAVRIC Shielding Tools •Replaces MORSE and SAS sequences – Introduced with SCALE 6 (Jan 2009) – Significant improvements in SCALE 6.1 (Jun 2011) •Monaco –Monte Carlo transport – Based on MORSE/KENO physics – SCALE General Geometry Package (SGGP), same as KENO-VI •MAVRIC –Sequence of Denovoand Monaco
PowerPoint Presentation
Introduction Monaco — multi-group Monte Carlo code MORSE physics SCALE Generalized Geometry Package (same as KenoVI) MAVRIC — Automated Variance Reduction CADIS Methodology GTRUNCL3D and TORT Monaco for Monte Carlo Calculation GeeWiz — the Windows GUI for using many SCALE programs Monaco/MAVRIC will be part of SCALE 6
MAVRIC/Monaco
•Review the different MAVRIC/Monaco output files and identify the location of different types of requested output •Introduce attendees to the SCALE plotting packages applicable to MAVRIC/Monaco output and demonstrate how to create commonly used output plots
Scale 6.1
The MeshView multiplatform interface produces 2D contour views of mesh data and mesh results from Monaco and KENO, and ChartPlot provides for energy-dependent plots of Monaco results. The ExSITE tool provides a dynamic multiplatform interface for the sensitivity and uncertainty analysis tools TSUNAMI-IP, TSURFER, and TSAR.
Monaco/MAVRIC: Computational Resources for
Monaco is the result of a modernization effort combining the multi-group neutron and photon physics of MORSE with the flexibility of the second-order surface SCALE general geometry package (SGGP), which is shared with KENO-VI.
8.2. Monaco: A Fixed-Source Monte Carlo Transport
Monaco is a general-purpose, fixed-source, Monte Carlo shielding code for the SCALE package. It is a functional module that uses either AMPX cross sections or continuous energy libraries to calculate neutron and photon fluxes and
8.2. Monaco: A Fixed-Source Monte Carlo Transport Code for
Monaco is a general-purpose, fixed-source, Monte Carlo shielding code for the SCALE package. It is a functional module that uses either AMPX cross sections or continuous energy libraries to
4.1. MAVRIC: Monaco with Automated Variance Reduction using
The forward Monte Carlo transport is performed using Monaco, a fixed-source shielding code that uses the SCALE General Geometry Package (SGGP, the same as used by the criticality code
SCALE 6.2.4
SCALE provides a suite of computational tools for criticality safety analysis that is primarily based on the KENO Monte Carlo code for eigenvalue neutronics calculations. Two variants of KENO provide identical solution capabilities with different geometry packages.
Monaco/MAVRIC: Computational Resources for Radiation
Monaco is the result of a modernization effort combining the multi-group neutron and photon physics of MORSE with the flexibility of the second-order surface SCALE general geometry package (SGGP), which is shared with KENO-VI. Monaco uses the same cross section package as other SCALE modules.
4.1. MAVRIC: Monaco with Automated Variance Reduction using
The forward Monte Carlo transport is performed using Monaco, a fixed-source shielding code that uses the SCALE General Geometry Package (SGGP, the same as used by the criticality code KENO-VI) and the standard SCALE material information processor. Monaco can use either MG or CE cross section libraries.
8. Monte Carlo Transport — SCALE 6.3.2 documentation
Monaco provides multiple methods to enter the radioactive source descriptions. Spatial distribution options include volumetric sources and mesh sources which can be generated by other codes such as KENO. Energy distributions can be entered by the user or imported directly from emission data provided by ORIGEN.
8.2. Monaco: A Fixed-Source Monte Carlo Transport Code for
Monaco is a general-purpose, fixed-source, Monte Carlo shielding code for the SCALE package. It is a functional module that uses either AMPX cross sections or continuous energy libraries to calculate neutron and photon fluxes and responses to specific geometry regions, to point detectors and to mesh tallies.
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