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The Concept Study on the New Steam Cooling Reactor

[+] Author Affiliations
Xuesong Yan, Xunchao Zhang, Yaling Zhang, Yangyang Yang, Lei Yang

Chinese Academy of Sciences, Lanzhou, China

Wenshan Duan

Northwest Normal University, Lanzhou, China

Paper No. ICONE25-67868, pp. V005T05A054; 5 pages
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5783-0
  • Copyright © 2017 by ASME


Coolant is an important part of the nuclear reactor, which can convert the fission energy into heat. At the same time, it can cool the core, and control the various components of the reactor in the allowable temperature. In this paper, gas-liquid two-phase flow is proposed as the coolant in the nuclear reactor. Based on the Monte Carlo method of particle transport program GMT program and LITAC program, the neutron performance, thermal hydraulic of nuclear reactor were calculated and analyzed. The operation of the new reactor will not be refuel for decades. The gas-liquid two-phase flow coolant can be used as one of the existing alternative coolants.

Copyright © 2017 by ASME



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