2011
DOI: 10.13182/nt174-289
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Monte Carlo Shielding Analysis Capabilities with MAVRIC

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Cited by 79 publications
(38 citation statements)
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“…Thus, in order to model the Co-60 source in multi-group calculations an energy conserving gamma spectrum was calculated for the 47 gamma group library available in the SCALE 6 package with ORIGEN-ARP 6.1. Dose rates were then calculated with the MAVRIC [2] sequence of SCALE 6.1.3 using point tallies and the v7-200n47g shielding library based on ENDF/B-VII data. However, SCALE/MAVRIC 6.2 offers the possibility to use continuous energy cross sections in the transport calculation which allowed us to model the Co-60 source without any pre-processing of the spectrum.…”
Section: Calculation Methods and Modelmentioning
confidence: 99%
“…Thus, in order to model the Co-60 source in multi-group calculations an energy conserving gamma spectrum was calculated for the 47 gamma group library available in the SCALE 6 package with ORIGEN-ARP 6.1. Dose rates were then calculated with the MAVRIC [2] sequence of SCALE 6.1.3 using point tallies and the v7-200n47g shielding library based on ENDF/B-VII data. However, SCALE/MAVRIC 6.2 offers the possibility to use continuous energy cross sections in the transport calculation which allowed us to model the Co-60 source without any pre-processing of the spectrum.…”
Section: Calculation Methods and Modelmentioning
confidence: 99%
“…The MAVRIC hybrid shielding sequence is based on CADIS methodology and its generalization with forward flux weighting is FW-CADIS. Excellent recent papers on methodologies were done by scientists at Oak Ridge National Laboratory [16,17]. CADIS and FW-CADIS are based on the concept of the importance function which is the solution of the adjoint Boltzmann transport equation [2,4].…”
Section: The Scale61 Code Packagementioning
confidence: 99%
“…To correctly account for how many source photons are released per source neutron, the system ]-parameter calculated by KENO-VI was used (2.46 neutrons/fission) with eff = 1.00012 ± 0.00013. The activated primary coolant becomes additional gamma emitter in operating reactor, since the product of (n, p) reaction with 16 spectrum of the activated nitrogen 16 N * which accounts for 94-97% of the total coolant activity. Using the total coolant volume of 1.53 ⋅ 10 8 cm 3 , its total mass of 1.21 ⋅ 10 8 g, and its working density of 0.79 g/cm 3 , we obtained total gamma source strength of 1.02⋅10 14 photons/s.…”
Section: Definition Of Ionizing Sourcesmentioning
confidence: 99%
“…Monaco is a fixed-source Monte Carlo shielding code that calculates neutron and photon fluxes and response functions for specific geometry regions, point detectors, and mesh tallies (Peplow, 2011). In addition, Monaco has variance reduction capabilities, such as source biasing and weight windows, which can be automated via the MAVRIC sequence (Monaco with Automated Variance Reduction using Importance Calculations).…”
Section: Shielding Analysismentioning
confidence: 99%
“…SCALE 6.2 will provide several new capabilities and significant improvements in many existing features, especially with expanded CE Monte Carlo capabilities for criticality safety, shielding, depletion, and sensitivity and uncertainty analysis. SCALE provides separate Monte Carlo capabilities for eigenvalue neutronics and fixed-source coupled neutron-gamma calculations, in the KENO and Monaco codes, respectively (Goluoglu et al, 2011;Peplow, 2011). Although the eigenvalue and fixed-source capabilities are provided in separate codes, there are many capabilities that are shared between them, including physics and geometry packages.…”
Section: Introductionmentioning
confidence: 99%