Influence of specimen size/type on the fracture toughness of five irradiated RPV materials
Creators
- 1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- 2. National Inst. of Standards and Technology (NIST), Boulder, CO (United States)
Description
The Heavy-Section Steel Irradiation (HSSI) Program had previously irradiated five reactor pressure vessel (RPV) steels/welds at fast neutron fluxes of about 4 to 8 x 1011 n/cm2/s (>1 MeV) to fluences from 0.5 to 3.4 1019 n/cm2 and at 288 °C. The unirradiated fracture toughness tests were performed by Oak Ridge National Laboratory with 12.7-mm and 25.4-mm thick (0.5T and 1T) compact specimens, while the HSSI Program provided tensile and 5 x 10-mm three-point bend specimens to SCK-CEN for irradiation in the in-pile section of the Belgian Reactor BR2 at fluxes > 1013 n/cm2/s and subsequent testing by SCK-CEN. The BR2 irradiations were conducted at about 2 and 4 x 1013 n/cm2/s with irradiation temperature between 295 °C and 300 °C (water temperature), and to fluences between 6 and 10 x 1019n/cm2. The irradiation-induced shifts of the Master Curve reference temperatures, ΔT0, for most of the materials deviated from the embrittlement correlations much more than expected, motivating the testing of 5 x 10-mm three-point bend specimens of all five materials in the unirradiated condition to eliminate specimen size and geometry as a variable. Tests of the unirradiated small bend specimens resulted in Master Curve reference temperatures, ΔT0, 25 °C to 53 °C lower than those from the larger compact specimens, meaning that the irradiation-induced reference temperature shifts, ΔT0, were larger than the initial measurements, resulting in much improved agreement between the measured and predicted fracture toughness shifts.
Files
47081666.pdf
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(2.5 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- OSTIID--1224752
Conference
- Title
- 17. international conference on environmental degradation of materials in nuclear power systems water reactors
- Dates
- 9-13 Aug 2015
- Place
- Ottawa, ON (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 47081666
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORRELATIONS; EMBRITTLEMENT; FAST NEUTRONS; FRACTURE PROPERTIES; MEV RANGE 01-10; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; SHAPE; SIZE; STEELS; TEMPERATURE RANGE 0400-1000 K; TESTING
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; CONTAINERS; ELEMENTARY PARTICLES; ENERGY RANGE; FERMIONS; HADRONS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; MEV RANGE; NEUTRONS; NUCLEONS; RADIATION EFFECTS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS
Optional Information
- Contract/Grant/Project number
- AC05-00OR22725
- Funding organization
- USDOE (United States)