Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2020, Vol. 31 ›› Issue (8): 74 doi: 10.1007/s41365-020-00789-4


Neutronic calculations of the China dual-functional lithium–lead test blanket module with the parallel discrete ordinates code Hydra

Guang-Chun Zhang1,2 • Jie Liu1,2 • Liang-Zhi Cao3,4 • Hong-Chun Wu3 • Xian-Bao Yuan4   

  1. 1 Science and Technology on Parallel and Distributed Processing Laboratory, National University of Defense Technology, Changsha 410073, China
    2 Laboratory of Software Engineering for Complex Systems, National University of Defense Technology, Changsha 410073, China
    3 School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
    4 College of Mechanical and Power Engineering, China Three Gorges University, Yichang 443002, China
  • Received:2020-03-25 Revised:2020-05-20 Accepted:2020-05-26
  • Contact: Liang-Zhi Cao
  • Supported by:
    This work was supported by the National Key Research and Development Program of China (Nos. 2018YFB0204301, 2017YFB0202104, and 2017YFE0302200).
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Guang-Chun Zhang, Jie Liu, Liang-Zhi Cao, Hong-Chun Wu, Xian-Bao Yuan. Neutronic calculations of the China dual-functional lithium–lead test blanket module with the parallel discrete ordinates code Hydra.Nuclear Science and Techniques, 2020, 31(8): 74     doi: 10.1007/s41365-020-00789-4

Abstract: The China dual-functional lithium–lead test blanket module (DFLL-TBM) is a liquid LiPb blanket concept developed by the Institute of Nuclear Energy Safety Technology of the Chinese Academy of Sciences for testing in ITER to validate relevant tritium breeding and shielding technologies. In this study, neutronic calculations of DFLL-TBM were carried out using a massively parallel three-dimensional transport code, Hydra, with the Fusion Evaluated Nuclear Data Library/MG. Hydra was developed by the Nuclear Engineering Computational Physics Lab based on the discrete ordinates method and has been devoted to neutronic analysis and shielding evaluation for nuclear facilities. An in-house Monte Carlo code (MCX) was employed to verify the discretized calculation model used by Hydra for the DFLL-TBM calculations. The results showed two key aspects: (1) In most material zones, Hydra solutions are in good agreement with the reference MCX results within 1%, and the maximal relative difference of the neutron flux is merely 3%, demonstrating the correctness of the calculation model; (2) while the current DFLL-TBM design meets the operation shielding requirement of ITER for 4 years, it does not satisfy the tritium self-sufficiency requirement. Compared to the two-step approach, Hydra produces higher accuracies as it does not rely on the homogenization technique during the calculation process. The parallel efficiency tests of Hydra using the DFLL-TBM model also showed that this code maintains a high parallel efficiency on O(100) processors and, as a result, is able to significantly improve computing performance through parallelization. Parameter studies have been carried out by varying the thickness of the beryllium armor layer and the tritium breeding zone to understand the influence of the beryllium layer and breeding zone thickness on tritium breeding performance. This establishes a foundation for further improvement in the tritium production performance of DFLL-TBM.

Key words: Discrete ordinates method, DFLL-TBM, Neutronic analysis, Tritium breeding performance