MODELING OF EXCESS REACTIVITY TRANSIENTS IN THE SEALER LEAD-COOLED REACTOR
4th International Technical Meeting on Small Reactors - 2016 Nov. 02-04


Presented at:
4th International Technical Meeting on Small Reactors
2016 Nov. 02-04
Location:
Ottawa, ON Canada
Session Title:
Parallel Session A:3 - SMR Reactor Physics

Authors:
A. Zhuchkova (Reactor Physicist)
N. Chornoboy (Research Scientist)
S. Golesorkhi (Reactor Physics Analyst)
  

Abstract

Modeling of the two hypothetical excess reactivity accidents was performed for the SEALER small lead-cooled reactor concept. The reactivity transient due to the leakage of steam from a steam generator to the core was analyzed using the SERPENT code. The ejection of the control rod assembly accident was modeled with the DONJON and DRAGON codes. The results of these two studies will be presented.

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