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Title: Neutronic reactor thermal shield

1. The method of operating a water-cooled neutronic reactor having a graphite moderator which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40-60 volume percent of the mixture, in contact with the graphite moderator.
Authors:
 [1]
  1. (West Chester, PA)
Publication Date:
OSTI Identifier:
862606
Report Number(s):
US 3971699
DOE Contract Number:
W-31-109-ENG-52
Resource Type:
Patent
Research Org:
Knolls Atomic Power Lab
Country of Publication:
United States
Language:
English
Subject:
neutronic; reactor; method; operating; water-cooled; neutronic; reactor; graphite; moderator; comprises; flowing; gaseous; mixture; carbon; dioxide; helium; helium; comprises; 40-60; volume; percent; mixture; contact; graphite; moderator; neutronic reactor; neutronic reactor; volume percent; gaseous mixture; carbon dioxide /376/976/