Electric heater for nuclear fuel rod simulators
Patent
·
OSTI ID:864185
- Knoxville, TN
- Concord, TN
The present invention is directed to an electric cartridge-type heater for use as a simulator for a nuclear fuel pin in reactor studies. The heater comprises an elongated cylindrical housing containing a longitudinally extending helically wound heating element with the heating element radially inwardly separated from the housing. Crushed cold-pressed preforms of boron nitride electrically insulate the heating element from the housing while providing good thermal conductivity. Crushed cold-pressed preforms of magnesia or a magnesia-15 percent boron nitride mixture are disposed in the cavity of the helical heating element. The coefficient of thermal expansion of the magnesia or the magnesia-boron nitride mixture is higher than that of the boron nitride disposed about the heating element for urging the boron nitride radially outwardly against the housing during elevated temperatures to assure adequate thermal contact between the housing and the boron nitride.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Number(s):
- US 4326122
- OSTI ID:
- 864185
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
/219/29/338/376/976/
adequate
assure
boron
boron nitride
cartridge-type
cavity
coefficient
cold-pressed
comprises
conductivity
contact
containing
crushed
cylindrical
cylindrical housing
directed
disposed
electric
electric heat
electric heater
electrically
electrically insulate
element
elevated
elevated temperature
elevated temperatures
elongated
elongated cylindrical
expansion
extending
fuel
fuel rod
heater
heating
heating element
helical
helically
helically wound
housing
housing containing
insulate
inwardly
longitudinally
longitudinally extending
magnesia
magnesia-15
magnesia-boron
mixture
nitride
nuclear
nuclear fuel
outwardly
percent
percent boron
preforms
providing
radially
radially inward
radially inwardly
radially outward
radially outwardly
reactor
reactor studies
rod
separated
simulator
simulators
studies
temperatures
thermal
thermal conductivity
thermal contact
thermal expansion
type heat
urging
wound
wound heat
adequate
assure
boron
boron nitride
cartridge-type
cavity
coefficient
cold-pressed
comprises
conductivity
contact
containing
crushed
cylindrical
cylindrical housing
directed
disposed
electric
electric heat
electric heater
electrically
electrically insulate
element
elevated
elevated temperature
elevated temperatures
elongated
elongated cylindrical
expansion
extending
fuel
fuel rod
heater
heating
heating element
helical
helically
helically wound
housing
housing containing
insulate
inwardly
longitudinally
longitudinally extending
magnesia
magnesia-15
magnesia-boron
mixture
nitride
nuclear
nuclear fuel
outwardly
percent
percent boron
preforms
providing
radially
radially inward
radially inwardly
radially outward
radially outwardly
reactor
reactor studies
rod
separated
simulator
simulators
studies
temperatures
thermal
thermal conductivity
thermal contact
thermal expansion
type heat
urging
wound
wound heat