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Title: Reactor refueling containment system

A method of refueling a nuclear reactor whereby the drive mechanism is disengaged and removed by activating a jacking mechanism that raises the closure head. The area between the barrier plate and closure head is exhausted through the closure head penetrations. The closure head, upper drive mechanism, and bellows seal are lifted away and transported to a safe area. The barrier plate acts as the primary boundary and each drive and control rod penetration has an elastomer seal preventing excessive tritium gases from escaping. The individual instrumentation plugs are disengaged allowing the corresponding fuel assembly to be sealed and replaced.
 [1];  [2]
  1. (Greensburg, PA)
  2. (Pittsburgh, PA)
Issue Date:
OSTI Identifier:
United States of America as represented by United States (Washington, DC) NETL
Patent Number(s):
US 5412700
Contract Number:
Research Org:
National Energy Technology Laboratory, Pittsburgh, PA, and Morgantown, WV
Country of Publication:
United States
reactor; refueling; containment; method; nuclear; whereby; drive; mechanism; disengaged; removed; activating; jacking; raises; closure; head; barrier; plate; exhausted; penetrations; upper; bellows; seal; lifted; transported; safe; primary; boundary; control; rod; penetration; elastomer; preventing; excessive; tritium; gases; escaping; individual; instrumentation; plugs; allowing; corresponding; fuel; assembly; sealed; replaced; preventing excessive; drive mechanism; control rod; nuclear reactor; fuel assembly; closure head; reactor refueling; tritium gas; corresponding fuel; jacking mechanism; reactor whereby; upper drive; bellows seal; /376/