STARCORE NUCLEAR GENERATION IV HTGR
35th Annual CNS Conference - 2015 May 31 - June 3


Presented at:
35th Annual CNS Conference
2015 May 31 - June 3
Location:
Saint John, Canada
Session Title:
2A4 - Advanced Reactor Designs

Authors:
M. K. Yates (StarCore Nuclear)
F. Shahrokhi (AREVA)
D. A. Poole (StarCore Nuclear)
L. D. Eskin (StarCore Nuclear)
  

Abstract

 

StarCore Nuclear (StarCore) is developing a High Temperature Gas Cooled Reactor using TRISO fuel, prismatic graphite blocks and a helium primary loop. The design is currently evolving, with the intent of completing the conceptual design and submitting it to the Canadian Nuclear Safety Commission (CNSC) as part of a Vendor Design Review within one year. The paper will focus on the status and plans for the design of the reactor plant.



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