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Nuclear Science User Facilities 138 Figure 4. Typical irradiation test train containing CT tensile and TEM specimens. Accomplishments During this project several baseline SCC tests were completed on alloys X-750 and XM-19. Cold-worked 9.3 XM-19 was utilized to study potentially similar material property effects between neutron embrittlement phenomena and embrittlement induced by cold-working the material. In addition to SCC tests fracture toughness tests at temperature not in environment and tensile tests at temperature not in environment were conducted. Results of the SCC tests were compared to data produced at the General Electric Global Research Company as a means of benchmarking INLs capability to perform these highly specialized experiments. In all cases the measured crack growth rates from the INL tests compared favorably with those produced by the benchmark laboratory. Figure 2 shows typical SCC test results for alloy X-750 and Figure 3 shows a typical fracture toughness test for alloy X-750. Results of the XM-19 tests are not included here for the sake of brevity but may be found in INL Report INL EXT-11-24173 Revision 1 or in the EPRI BWRVessel Integrity Program Report 1025135 on the EPRI website. Phase II of this project involved exper- iment physics and safety analysis as well as test train design for irradiating the specimens.A report was issued in February 2012 showing the results of these analyses and descriptions of the test train designs Figure 4. The first irradiation was completed during 2013 on the EPRI-2 capsule with a target fluence of 2.0 x 1020 ncm2 E1MeV in Loop 2A of the ATR center flux trap.Actual measured fluence for this capsule was 1.93 x 1020 ncm2 . The capsule was shipped from ATR to the Hot Fuels Examination Facility HFEF following irradiation and cool down and was disassembled in preparation for PIE. In early 2014 the first of two irradia- tion cycles for the EPRI-3 capsule at a target fluence of 1.0 x 1021 ncm2 was completed also using Loop 2A in the ATR center flux trap. Complica- tions arising from a flow restriction have delayed completion of the second irradiation cycle but it is expected to be completed in 2015 along with the lowest fluence 5.0 x 1019 ncm2 irradiation of the EPRI-1 capsule. The very first test on the newly constructed IASCC test rig system was also conducted during 2014 on an X-750 specimen that was irradiated in the EPRI-2 capsule. This represented an exciting milestone for the project and for INL.Very stable crack propa- gation was measured and excellent chemistry control was exhibited in the new systems. The measured crack growth rates in this irradiated X-750 equal to nominally 3.1 6.2 x 10-8 mms in hydrogen water chemistry HWC and 1.1 22 x 10-7 mms in normal water chemistry NWC were comparable to CGRs that were previously measured in the same alloy in an un-irradiated state. Figure 5 shows a typical CGR plot for this very first IASCC test demonstrating the system chemistry control in switching between HWC and NWC.