Overview of the Savannah River reactor surveillance program
Preliminary radiation effects studies, now nearing completion, are based upon short-term irradiations in the High Flux Isotope Reactor (HFIR) and University of Buffalo Reactor (UBR). The purpose of these studies is to assess the impact of radiation effects on the performance and service life of Savannah River Site (SRS) reactor components. The SRS reactor surveillance program was simultaneously established in order to validate the results of these short-term irradiations under conditions more applicable to the SRS reactor components. The main conditions of interest include: temperature, moderator chemistry and neutron spectrum. The materials employed in both the surveillance and short-term irradiation programs were taken from the SRS R-reactor process piping and included base, weld, and heat-effected zone metal samples in both the C-L and L-C orientations. Test specimen types include tensile, Charpy V-notch, compact tension, constant extension rate test, and wedge-opening-load. A program schedule has been established for the irradiation and testing of surveillance specimens. The surveillance capsules are currently undergoing irradiation near the center of the SRS K-rector core and will remain in this location until their total fast fluence is equal to the current maximum reactor tank wall exposure. The bulk of the specimens will then be moved to blanket capsules at the edge of the core in order to track the wall exposure. A small portion of the specimens will be removed and tested, and a third group of specimens will be removed from the central core position after they have accumulated a thermal fluence 50% greater than the current maximum tank wall exposure. Specimen groups will be removed from the blanket capsules and tested periodically. Additional capsules may be inserted in order to generate flow fluence or high thermal to fast flux ratio data. 17 refs.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10142128
- Report Number(s):
- WSRC-MS-91-270; CONF-920631-29; ON: DE92013195
- Resource Relation:
- Conference: American Society of Mechanical Engineers (ASME) pressure vessels and piping conference,New Orleans, LA (United States),21-25 Jun 1992; Other Information: PBD: [1991]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
R REACTOR
REACTOR COMPONENTS
STAINLESS STEEL-304
PHYSICAL RADIATION EFFECTS
STAINLESS STEEL-308
TEST FACILITIES
HFIR REACTOR
PULSTAR-BUFFALO REACTOR
PIPES
REACTOR COOLING SYSTEMS
REACTOR CORES
NEUTRON FLUENCE
IRRADIATION
SERVICE LIFE
CHARPY TEST
MONITORING
BREEDING BLANKETS
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
220900
220600
360106
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
RADIATION EFFECTS