Reactor refueling containment system

Patent · Sun Jan 01 00:00:00 EST 1995

OSTI ID:869868

Gillett, James E ^[1]; Meuschke, Robert E ^[2]

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1. Greensburg, PA
2. Pittsburgh, PA

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.

• Research Organization: National Energy Technology Laboratory (NETL), Pittsburgh, PA, Morgantown, WV (United States)
• DOE Contract Number: AC02-90CH10440
• Assignee: United States of America as represented by United States (Washington, DC)
• Patent Number(s): US 5412700
• OSTI ID: 869868
• Country of Publication: United States
• Language: English

Related Subjects

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
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