Impact of radiation embrittlement on integrity of pressure vessel supports for two PWR (pressurized-water-reactor) plants
Recent pressure-vessel surveillance data from the High Flux Isotope Reactor (HFIR) indicate an embrittlement fluence-rate effect that is applicable to the evaluation of the integrity of light-water reactor (LWR) pressure vessel supports. A preliminary evaluation using the HFIR data indicated increases in the nil ductility transition temperature at 32 effective full-power years (EFPY) of 100 to 130/degree/C for pressurized-water-reactor (PWR) vessel supports located in the cavity at midheight of the core. This result indicated a potential problem with regard to life expectancy. However, an accurate assessment required a detailed, specific-plant, fracture-mechanics analysis. After a survey and cursory evaluation of all LWR plants, two PWR plants that appeared to have a potential problem were selected. Results of the analyses indicate minimum critical flaw sizes small enough to be of concern before 32 EFPY. 24 refs., 16 figs., 7 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6493331
- Report Number(s):
- CONF-8810155-41; ON: DE89006625
- Resource Relation:
- Conference: 16. water reactor safety information meeting, Gaithersburg, MD, USA, 24 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Radiation embrittlement of PWR vessel supports
Impact of radiation embrittlement on integrity of pressure vessel supports for two PWR plants
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRESSURE VESSELS
SUPPORTS
PWR TYPE REACTORS
RADIATION EFFECTS
EMBRITTLEMENT
FRACTURE MECHANICS
HFIR REACTOR
NEUTRON FLUX
REACTOR SAFETY
SERVICE LIFE
CONTAINERS
ENRICHED URANIUM REACTORS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MECHANICAL STRUCTURES
MECHANICS
RADIATION FLUX
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors