Between-cycle laser system for depressurization and resealing of modified design nuclear fuel assemblies
Patent
·
OSTI ID:864093
- Richland, WA
A laser beam is used to puncture fuel cladding for release of contained pressurized fission gas from plenum sections or irradiated fuel pins. Exhausted fission gases are collected and trapped for safe disposal. The laser beam, adjusted to welding mode, is subsequently used to reseal the puncture holes. The fuel assembly is returned to additional irradiation or, if at end of reactivity lifetime, is routed to reprocess. The fuel assembly design provides graded cladding lengths, by rows or arrays, such that the cladding of each component fuel element of the assembly is accessible to laser beam reception.
- Research Organization:
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
- DOE Contract Number:
- E(45-1)-2170
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Number(s):
- US 4309250
- OSTI ID:
- 864093
- Country of Publication:
- United States
- Language:
- English
Similar Records
Between-cycle laser system for depressurization and resealing of modified design nuclear fuel assemblies
Between-cycle laser system for depressurization and resealing of modified design nuclear fuel assemblies
Remote depressurization and resealing of GCFR F-5 fuel pins
Patent
·
Tue Jan 05 00:00:00 EST 1982
·
OSTI ID:864093
Between-cycle laser system for depressurization and resealing of modified design nuclear fuel assemblies
Patent
·
Tue Jan 05 00:00:00 EST 1982
·
OSTI ID:864093
Remote depressurization and resealing of GCFR F-5 fuel pins
Conference
·
Fri Jul 17 00:00:00 EDT 1981
·
OSTI ID:864093
Related Subjects
between-cycle
laser
depressurization
resealing
modified
design
nuclear
fuel
assemblies
beam
puncture
cladding
release
contained
pressurized
fission
gas
plenum
sections
irradiated
pins
exhausted
gases
collected
trapped
safe
disposal
adjusted
welding
mode
subsequently
reseal
holes
assembly
returned
additional
irradiation
reactivity
lifetime
routed
reprocess
provides
graded
lengths
rows
arrays
component
element
accessible
reception
fuel cladding
fuel assemblies
fuel element
nuclear fuel
laser beam
fuel assembly
fuel pins
irradiated fuel
design provides
fission gas
safe disposal
assembly design
fission gases
/376/976/
laser
depressurization
resealing
modified
design
nuclear
fuel
assemblies
beam
puncture
cladding
release
contained
pressurized
fission
gas
plenum
sections
irradiated
pins
exhausted
gases
collected
trapped
safe
disposal
adjusted
welding
mode
subsequently
reseal
holes
assembly
returned
additional
irradiation
reactivity
lifetime
routed
reprocess
provides
graded
lengths
rows
arrays
component
element
accessible
reception
fuel cladding
fuel assemblies
fuel element
nuclear fuel
laser beam
fuel assembly
fuel pins
irradiated fuel
design provides
fission gas
safe disposal
assembly design
fission gases
/376/976/