Pressure-vessel fluence reduction through selective fuel-assembly replacement
Conference
·
OSTI ID:6138688
The nil-ductility transition temperature (RT/sub NDT/) of a PWR pressure vessel (PV) increases during its lifetime due to neutron-induced radiation damage. If during a pressurized thermal shock (PTS) event the PV is cooled below its RT/sub NDT/ and then repressurized, the vessel may undergo brittle fracture. For several operating reactors it may be necessary to reduce this neutron-induced vessel damage in order to maintain the vessel RT/sub NDT/ below the range of concern. In this study the potential fluence (and hence damage) reduction achievable by selective replacement of peripheral fuel assemblies in which the fuel rods have been replaced by stainless steel rods is considered.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6138688
- Report Number(s):
- BNL-NUREG-33322; CONF-831047-52; ON: DE83015329
- Country of Publication:
- United States
- Language:
- English
Similar Records
On the uncertainity of neutron transport calculations for reactor pressure vessel surveillance
Pressure-vessel-damage fluence reduction by low-leakage fuel management. [PWR]
Using the LEPRICON System to Evaluate Best-Estimate Vessel Fluence at Ulchin NPP Unit 1
Journal Article
·
Mon Dec 30 23:00:00 EST 1996
· Transactions of the American Nuclear Society
·
OSTI ID:436886
Pressure-vessel-damage fluence reduction by low-leakage fuel management. [PWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5756784
Using the LEPRICON System to Evaluate Best-Estimate Vessel Fluence at Ulchin NPP Unit 1
Conference
·
Sun Jun 04 00:00:00 EDT 2000
·
OSTI ID:786226
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALLOYS
CONTAINERS
DUCTILE-BRITTLE TRANSITIONS
FUEL MANAGEMENT
IRON ALLOYS
IRON BASE ALLOYS
NEUTRON FLUX
OPERATION
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTOR OPERATION
REACTORS
STEELS
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALLOYS
CONTAINERS
DUCTILE-BRITTLE TRANSITIONS
FUEL MANAGEMENT
IRON ALLOYS
IRON BASE ALLOYS
NEUTRON FLUX
OPERATION
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTOR OPERATION
REACTORS
STEELS
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS