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Study on Neutronic Characteristics and Neutronic-Thermohydraulic Coupling Behavior of SCWR With Thorium-Based Fuel

[+] Author Affiliations
Shichang Liu, Jiejin Cai

Sun Yat-sen University, Guangzhou, Guangdong, China

Paper No. ICONE21-15218, pp. V006T16A004; 10 pages
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 6: Beyond Design Basis Events; Student Paper Competition
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5583-6
  • Copyright © 2013 by ASME


A novel thorium-based fuel assembly for SCWR has been introduced in this paper, taking advantage of the neutron spectrum of SCWR. Single channel thermohydraulic model was integrated with calculation codes “dragon” and “donjon”, developing a computation platform for neutronics assessment and thermohydraulic analysis of the proposed fuel assembly.

Results show that the thorium-based fuel assembly meets design rules of SCWR. Meanwhile, it has considerable advantages on both efficient fuel utilization and lower minor actinide generation.

Copyright © 2013 by ASME



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