A Nodal-iterative Technique for Criticality Calculations in Multigroup Neutron Diffusion Models
Trends in Computational and Applied Mathematics, 2022 In this work, a nodal and iterative technique to evaluate the effective multiplication factor as well as the neutron flux, in multigroup diffusion problems, is presented.
R. Zanette +2 more
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Molten Salt Research Reactor (MSRR) shielding analysis using SCALE/MAVRIC sequence with continuous energy and multigroup cross sections [PDF]
EPJ Web of ConferencesIt is necessary to verify (and validate when experimental data are available) shielding codes and methodologies for Molten Salt Reactors (MSRs). This paper examines the impact of using a fine and coarse multigroup cross section library vs.
Petrovic Bojan +2 more
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A multigroup diffusion solver using pseudo transient continuation for a radiation-hydrodynamic code with patch-based AMR [PDF]
, 2007 We present a scheme to solve the nonlinear multigroup radiation diffusion (MGD) equations. The method is incorporated into a massively parallel, multidimensional, Eulerian radiation-hydrodynamic code with adaptive mesh refinement (AMR).
Aleksei I. Shestakov +24 more
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Current status of the verification and processing system GALILÉE-1 for evaluated data [PDF]
EPJ Web of Conferences, 2020 This paper describes the current status of GALILÉE-1 that is the new verification and processing system for evaluated data, developed at CEA. It consists of various components respectively dedicated to read/write the evaluated data whatever the format is,
Coste-Delclaux Mireille +2 more
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Frontiers in Psychology, 2022 Since rapid economic growth has led to the overuse of natural resources and environmental degradation, increasing attention has been paid to environmental problems.
Biao Luo, Liru Li, Ying Sun
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IMPROVEMENT OF SCALE-XSProc MULTIGROUP CROSS SECTION PROCESSING BASED ON THE CENTRM POINTWISE SLOWING DOWN CALCULATION [PDF]
EPJ Web of Conferences, 2021 The SCALE-XSProc multigroup (MG) cross section processing procedure based on the CENTRM pointwise slowing down calculation is the primary procedure to process problem-dependent self-shielded MG cross sections and scattering matrices for neutron transport
Kim Kang Seog +4 more
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Only reasoned action? An interorganizational study of energy-saving behaviors in office buildings [PDF]
, 2014 Substantial energy savings can be achieved by reducing energy use in office buildings. The reported study used a Theory of Planned Behavior (TPB) model extended with perceived habit to explain office energy-saving behaviors.
Kok, G +3 more
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The Dilution Dependency of Multigroup Uncertainties
Science and Technology of Nuclear Installations, 2014 The propagation of nuclear data uncertainties through reactor physics calculation has received attention through the Organization for Economic Cooperation and Development—Nuclear Energy Agency’s Uncertainty Analysis in Modelling (UAM) benchmark. A common
M. R. Ball +3 more
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Generating multi-group cross-sections using continuous-energy Monte Carlo method for fast reactor analysis [PDF]
EPJ Web of ConferencesThe deterministic two-step method, comprising multigroup cross-section generation and core calculation, is widely applied in fast reactor design and analysis.
Guo Hui +4 more
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Science and Technology of Nuclear Installations, 2020 For nuclear reactor physics, uncertainties in the multigroup cross sections inevitably exist, and these uncertainties are considered as the most significant uncertainty source. Based on the home-developed 3D high-fidelity neutron transport code HNET, the
Ji Ma, Chen Hao, Lixun Liu, Yuekai Zhou
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