Automatic safety rod for reactors
Patent
·
OSTI ID:866711
- San Jose, CA
An automatic safety rod for a nuclear reactor containing neutron absorbing material and designed to be inserted into a reactor core after a loss-of-core flow. Actuation is based upon either a sudden decrease in core pressure drop or the pressure drop decreases below a predetermined minimum value. The automatic control rod includes a pressure regulating device whereby a controlled decrease in operating pressure due to reduced coolant flow does not cause the rod to drop into the core.
- Research Organization:
- GENERAL ELECTRIC CO
- DOE Contract Number:
- AT03-76SF71032
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Number(s):
- US 4769208
- OSTI ID:
- 866711
- Country of Publication:
- United States
- Language:
- English
Similar Records
Automatic safety rod for reactors. [LMFBR]
Automatic safety rod for reactors
Nuclear reactor shutdown control rod assembly
Patent
·
Mon Mar 22 23:00:00 EST 1982
·
OSTI ID:6469290
Automatic safety rod for reactors
Patent
·
Tue Sep 06 00:00:00 EDT 1988
·
OSTI ID:6624500
Nuclear reactor shutdown control rod assembly
Patent
·
Mon Mar 28 23:00:00 EST 1988
·
OSTI ID:5075142
Related Subjects
/376/976/
absorbing
absorbing material
actuation
automatic
automatic control
automatic safety
based
below
containing
containing neutron
control
control rod
controlled
coolant
coolant flow
core
decrease
decreases
designed
device
device whereby
drop
due
flow
inserted
loss-of-core
material
minimum
neutron
neutron absorbing
nuclear
nuclear reactor
operating
operating pressure
predetermined
predetermined minimum
pressure
pressure drop
pressure due
pressure regulating
reactor
reactor containing
reactor core
reactors
reduced
regulating
regulating device
rod
safety
safety rod
sorbing material
sudden
value
whereby
absorbing
absorbing material
actuation
automatic
automatic control
automatic safety
based
below
containing
containing neutron
control
control rod
controlled
coolant
coolant flow
core
decrease
decreases
designed
device
device whereby
drop
due
flow
inserted
loss-of-core
material
minimum
neutron
neutron absorbing
nuclear
nuclear reactor
operating
operating pressure
predetermined
predetermined minimum
pressure
pressure drop
pressure due
pressure regulating
reactor
reactor containing
reactor core
reactors
reduced
regulating
regulating device
rod
safety
safety rod
sorbing material
sudden
value
whereby