Study on the calculational framework development of the advanced numerical reactor neutronics code SHARK
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Published:2023-01-11
Issue:
Volume:10
Page:
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ISSN:2296-598X
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Container-title:Frontiers in Energy Research
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language:
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Short-container-title:Front. Energy Res.
Author:
Hongbo Zhang,Wenbo Zhao,Chen Zhao,Bo Wang,Zhang Chen,Xingjie Peng,Qing Li,Yingrui Yu,Zhaohu Gong,Wei Zeng
Abstract
The SHARK program (Simulation-based High-fidelity Advanced Reactor physics Kit) is a high-fidelity heterogeneous neutronics code for the numerical reactor system being developed at the Nuclear Power Institute of China (NPIC). The program uses a Constructive Solid Geometry (CSG) framework to model various complex geometries. To enhance the flexibility and robustness during continuous development process, SHARK program attempts to support a rich set of methods, tools and library options within a unified general framework as a “toolkit”. For the multi-core clustered supercomputer architectures that are commonly used today, the SHARK program adopts a hybrid parallel strategy of MPI and OpenMP to achieve complementary advantages between them. In addition, the framework of SHARK program is designed with a true object-oriented manner. Through reasonable abstraction, inheritance and encapsulation, the maintainability and extensibility of the code are improved, and long-term team development is facilitated. Up to now, key modules for cross-section generation, heterogeneous transport calculation and microscopic depletion have been developed under the general frameworks. The main features of SHARK’s “resonance-transport-depletion” coupling system are elaborated in this paper, and some verification and validation (V&V) results in the current phase are presented and discussed.
Publisher
Frontiers Media SA
Subject
Economics and Econometrics,Energy Engineering and Power Technology,Fuel Technology,Renewable Energy, Sustainability and the Environment
Reference27 articles.
1. Coupled MC21 and COBRA-IE solution to VERA core physics benchmark problem# 6[C];Aviles,2016
2. The OpenMOC The OpenMOC method of characteristics neutral particle transport codeethod of characteristics neutral particle transport code;Boyd;AnnAnn. Nucl. Energy Nucl. Energy,2014
3. Nuclear reactor multi-physics simulations with coupled MCNP5 and STAR-CCM+[D];Cardoni,2011
4. The log linear rate constant power depletion method [C];Carpenter,2010
5. Development and preliminary V&V for advanced neutron transport lattice code KYLIN-2 [J];Chai;High Power Laser Part. Beams (in Chinese),2017