NSUF 20-EPRI-I-II-III: NSUF and EPRI Pilot Project

These materials are the subject of this collaborative pilot project between the Electric Power Research Institute (EPRI) and Idaho National Laboratory Alloys X-750 and XM-19 materials are used as original equipment or repair hardware in BWR internals. Very little stress corrosion crack growth and irradiated fracture toughness data exists for Alloy X-750 and XM-19 at the exposure levels of interest, up to 1x1021 n/cm2. These materials are the subject of this project to generate such data in BWR environments and to understand the effects of neutron irradiation. Phase 1 of this pilot project develops baseline fracture toughness and crack growth rates of unirradiated material. Results from Phase 1 will be compared with results generated by another laboratory to confirm consistency in the data and testing procedures. Phase 2 involves the design and safety analysis on the test apparatus for the irradiation of tensile and compact tension specimens in the ATR. Phase 3 of this project will perform irradiation and conduct post-irradiation testing of the materials.

Допълнителна информация

Поле	Стойност
Awarded Institution	None
Embargo End Date	2028-07-01
Facility Tech Lead	Alina Montrose
NSUF Call	Library Submission
PI	None
Project Member
Project Notes	Cycles: EPRI-I = CYCLE 157C; EPRI-2 = CYCLE 153B; EPRI-3 = CYCLES 155B,158B. EPRI-3 average irradiation temperature is expected to be the temperature at which the specimens were held for a majority of the time (see Technical Report INL/EXT-20-58432). EPRI-3 As-Run irradiation conditions (Temp, Dose, Flux, and Fluence) are averages of both cycles (155B and 158B).
Project Type	Library Submission