Advancing Core Safety of Gen IV and Gen IV + Reactors by Encompassing High-Temperature Resistant Materials - 18673
The paper focuses on the development of materials for Gen IV/IV+ reactor core. It discusses the advancement of materials studied and their application in different components of the reactor core and other auxiliary components which will help in the development of future generation reactors. The paper summarizes the material study showing the characteristic behavior of different materials (coated with FeB and FeB{sub 2}), towards irradiation at near high temperatures and high energy neutron flux condition. The project includes different materials which are coated on the boundaries with varied thickness of FeB and FeB{sub 2}. The samples included Carbon steel, Stainless steel 310, Stainless steel 316, Inconel 718. All above-mentioned samples were received by Prof. J. Szpunar, through an industry with coatings of FeB and FeB{sub 2} with varied thickness along with a bare sample of each material. The samples were irradiated at the University of Saskatchewan reactor, with fast neutron flux of 1.1x10{sup 11} n.cm{sup -2}.sec{sup -1}. I worked on all the samples but the paper particularly focuses on, two carbon steel samples results, received so far. The methodology for the project been followed for all the samples is as follow: 1. Received samples were first polished. 2. Vickers Hardness Test. 3. Mirror polished. 4. Etched with the appropriate etchant for the material. 5. Microscopic study of the etched surface. 6. SEM imaging. 7. Sent for irradiation. 8. The same set of material testing done after irradiation, with an EBSD run on the boundary and main surface. The two Carbon Steel samples (sample 21 and 19) analyzed, were irradiated for 14 hrs. Sample 21 was a bare sample and sample 19 had a coating of FeB, FeB{sub 2} with a ∼0.0010'' thickness. The methodology was followed for material testing before and after the irradiation. The advantage of FeB and FeB{sub 2} coatings are: 1. Higher hardness - 10 times (FeB-1775 and FeB{sub 2}-1450), 2. High-stress capacity, 3. Lower abrasion, 4. Low corrosion. Through the test results obtained before and after the irradiation, I was able to get a view of coating damage at the boundaries of sample 19. The bare sample don't show any difference after irradiation but the coated sample do show cracks in the FeB layer. Which can be seen in the SEM images of sample 19. The hardness results are promising, as hardness didn't change significantly. The hardness test was done on the substrate as the coating was significantly narrow to perform the test. Though the hardness test on coatings was performed by the possessor company which show hardness higher by a factor of 10 when compared to uncoated surfaces. The XRD results, reveal irradiation effect on the crystal lattice, making it deformed, which though is usual during irradiation. The overall analysis along with EBSD done on the two samples are favorable and promising. Though it still needs to be cleared out, whether the cracks on the coating were due to irradiation or due to etching after the samples were irradiated.