Efficient visualization of high-resolution virtual nuclear reactor

Cao, Yi; Mo, Zeyao; Xiao, Li; Wang, Huawei; Ai, Zhiwei; Zhang, Zhe

doi:10.1007/s12650-018-0487-1

Cited by 4 publications

(2 citation statements)

References 12 publications

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“…The lower floor comprises the two support frameworks of JASMIN [2] and JCOGIN [1]. The unified CAD preprocessor JLAMT [14] and view postprocessor TeraVAP [15] are equipped for the JPTS (see Fig. 1).…”

Section: Jmct Systemmentioning

confidence: 99%

A high fidelity general purpose 3-D Monte Carlo particle transport program JMCT3.0

Deng

Zhang

et al. 2022

NUCL SCI TECH

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JMCT is a large-scale, high-fidelity, three-dimensional general neutron–photon–electron–proton transport Monte Carlo software system. It was developed based on the combinatorial geometry parallel infrastructure JCOGIN and the adaptive structured mesh infrastructure JASMIN. JMCT is equipped with CAD modeling and visualizes the image output. It supports the geometry of the body and the structured/unstructured mesh. JMCT has most functions, variance reduction techniques, and tallies of the traditional Monte Carlo particle transport codes. Two energy models, multi-group and continuous, are provided. In recent years, some new functions and algorithms have been developed, such as Doppler broadening on-the-fly (OTF), uniform tally density (UTD), consistent adjoint driven importance sampling (CADIS), fast criticality search of boron concentration (FCSBC) domain decomposition (DD), adaptive control rod moving (ACRM), and random geometry (RG) etc. The JMCT is also coupled with the discrete ordinate SN code JSNT to generate source-biasing factors and weight-window parameters. At present, the number of geometric bodies, materials, tallies, depletion zones, and parallel processors are sufficiently large to simulate extremely complicated device problems. JMCT can be used to simulate reactor physics, criticality safety analysis, radiation shielding, detector response, nuclear well logging, and dosimetry calculations etc. In particular, JMCT can be coupled with depletion and thermal-hydraulics for the simulation of reactor nuclear-hot feedback effects. This paper describes the progress in advanced modeling, high-performance numerical simulation of particle transport, multiphysics coupled calculations, and large-scale parallel computing.

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Section: Jmct Systemmentioning

confidence: 99%

A high fidelity general purpose 3-D Monte Carlo particle transport program JMCT3.0

Deng

Zhang

et al. 2022

NUCL SCI TECH

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“…Operation guides for NPP controls Virtual operator training [13]; Path planning and maintenance guiding simulation [14]; Refueling plant training [15]; Virtual roaming simulation and organ dose evaluation [16] Emergency handling in an NPP Seismic analysis of an NPP [17,18]; Emergency path planning [19]; Security simulation [20]; Egress simulation [21] Reference models for NPP construction Conical roof lifting for an NPP [22]; Reactor modeling [23] As shown in Table 1, most of the virtual applications in an NPP are classified into three fields: operation guides, reference models for constructions, and emergency handling. However, the ergonomic research studies using virtual applications have been immature in the nuclear power field.…”

Section: Virtual Model Application Area Research Studies and Systemsmentioning

confidence: 99%

Virtual Reality-Based Ergonomic Modeling and Evaluation Framework for Nuclear Power Plant Operation and Control

Lee

Chang

2019

Sustainability

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The purpose of this study is to introduce a new and efficient virtual model-based ergonomic simulation framework utilizing recent anthropometric data for a digitalized main control room in an advanced nuclear power plant. The system interface of the main control room has been undergoing digitalization via various information and control consoles. Console operators often face human–computer interactive problems due to inappropriate console design. Computational models with a process of visual perception and variables of anthropometric data are developed for designing and evaluating operator consoles with the requirements of human factor guidelines. From the 3D computational model and simulation application, console dimensions and a designing test module, which would be used for designing suitable consoles with safety concerns in a nuclear plant, are proposed. To efficiently carry out console design and evaluation feedback, an intelligent design review system comprising a virtual modeling and simulation framework is developed. The proposed automated and virtual design review system provides console design efficiency and evaluation effectiveness. This study may influence methods of employing suitable design concepts with various anthropometric data in many areas with safety concerns and may show a feasible solution to designing and evaluating the main control room.

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Feature-preserving mesh simplification through anisotropic Nyquist-based adaptive sampling of points inside the segmented regions

Asgharian

Ebrahimnezhad

2022

J Vis

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Efficient visualization of high-resolution virtual nuclear reactor

Cited by 4 publications

References 12 publications

A high fidelity general purpose 3-D Monte Carlo particle transport program JMCT3.0

A high fidelity general purpose 3-D Monte Carlo particle transport program JMCT3.0

Virtual Reality-Based Ergonomic Modeling and Evaluation Framework for Nuclear Power Plant Operation and Control

Feature-preserving mesh simplification through anisotropic Nyquist-based adaptive sampling of points inside the segmented regions

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