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Development of High-Fidelity Neutron Transport Solver of Alpha

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Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3

Part of the book series: Springer Proceedings in Physics ((SPPHY,volume 285))

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Abstract

To achieve the high-fidelity and high-performance neutronics simulation of complex assemblies and whole-core problems, the lattice physics code ALPHA (Advanced Lattice Physics code based on Heterogeneous Architecture) is developed. ALPHA employs the planar method of characteristic (MOC) with the axial flux expansion (MOC-EX) scheme to perform 3D problems. The coarse mesh finite difference (CMFD) scheme is used to accelerate the transport sweeping numerically. The heterogeneous system architecture (HSA) has been a powerful tool to accelerate numerous scientific computing applications. Motivated by this, the transport solver of ALPHA is parallelized on the CPU/GPU heterogeneous platform. To exploit the computing capability of the GPU, some optimizations are investigated and implemented on MOC parallel algorithm. In this paper, the implementation, verification, and validation of the neutron transport solver built-in ALPHA are presented.

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Acknowledgements

This work is supported by the fund provided by the National Natural Science Foundation of China [12105063], the Science and Technology on Reactor System Design Technology Laboratory [HT-KFKT-02-2019004], the Stability Support Fund for Key Laboratory of Nuclear Data [JCKY2021201C154] and the Natural Science Foundation of Heilongjiang Province of China [LH2020A001].

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Correspondence to Qiang Zhao .

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Zou, H., Zhang, Q., Song, P., Liang, L., Zhao, Q. (2023). Development of High-Fidelity Neutron Transport Solver of Alpha. In: Liu, C. (eds) Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3. Springer Proceedings in Physics, vol 285. Springer, Singapore. https://doi.org/10.1007/978-981-19-8899-8_98

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