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Thermal Hydraulic Analysis of a SCWR Core Concept

[+] Author Affiliations
Weizhong Zhang

Shanghai Nuclear Engineering Research and Design Institute, Shanghai, China

Paper No. ICONE21-16217, pp. V002T05A046; 9 pages
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5579-9
  • Copyright © 2013 by ASME


A Super Critical Water Reactor (SCWR) single channel analysis model was built considering energy coupling between water rods and coolant channels. By using this model, a comparative study was performed on SCWR fuel assembly arrangement such as the size and location of water rods and fuel pins. Cladding temperature, pellet centerline temperature, and coolant core-outlet velocity were selected as comparison criteria. Preliminary core conceptual design of 1000 MWe SCWR was carried out and two sets of main parameters for SCWR core were proposed.

Copyright © 2013 by ASME



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