Monte Carlo capabilities of the SCALE code system

Abstract

a b s t r a c t 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, licensees, 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 can be selected based on the desired solution, including hybrid deterministic/ Monte Carlo simulations. SCALE includes the latest nuclear data libraries for continuous-energy and multigroup radiation transport as well as activation, depletion, and decay calculations. SCALE's graphical user interfaces assist with accurate system modeling, visualization, and convenient access to desired results. SCALE 6.2 will provide several new capabilities and significant improvements in many existing features, especially with expanded continuous-energy Monte Carlo capabilities for criticality safety, shielding, depletion, and sensitivity and uncertainty analysis. An overview of the Monte Carlo capabilities of SCALE is provided here, with emphasis on new features for SCALE 6.2.

Superphénix Benchmark Part I: Results of Static Neutronics

“…The 3D Superphe `nix core model created for KENO-VI is equivalent to the SERPENT model where no geometrical simplifications were made. As implemented in SCALE6.2 [8], KENO-VI has the capability of providing problem-dependent temperature corrections to the pointwise data by means of a Doppler broadening treatment so that small temperature perturbations are feasible. Continuous energy KENO-VI simulations have included 1 Â 10 6 neutrons in 400 active generations and 200 skipped cycles ensuring an eigenvalue statistical uncertainty lower than 5 pcm.…”

Improvement of Geant4 Neutron-HP package: from methodology to evaluated nuclear data library

“…To this aim, the nuclear industry and nuclear engineering laboratories have been developing and using for decades dedicated Monte Carlo neutron transport codes, relying on evaluated nuclear data and subsequent nuclear data processing and treatment. Among these neutronics reference codes, MNCP (version 5 [6] and 6 [7]), SCALE [8], SERPENT [9], MORET (version 5 [10] and 6 [11]) or TRIPOLI-4 ® [12] are validated and qualified using inter-code comparisons (see for instance [13]) and large qualification data bases (using either integral or differential experiments). Combined with a large user community, these codes hence present coherent results in their respective qualification domains.…”

Estudo da viabilidade da alteração da posição da câmara de fissão no reator IEA-R1

“…O ambiente SCALE, desenvolvido e mantido pelo Laboratório Nacional de Oak Ridge (ORNL), se trata de um conjunto de ferramentas voltadas para as mais diversas aplicações na área nuclear, como física nuclear, criticalidade, caracterização de combustível usado, blindagem, análise de sensibilidade e incertezas (REARDEN et al, 2015). A Erro!…”