Analysis of mechanical properties of short pin PWR dummy post irradiation.

Autor: Ismarwanti, Sri, Ajiriyanto, Maman Kartaman, Sigit, Rohmad, Setiawan, Jan, Guswardani, Guswardani, Purwanta, Purwanta, Sihotang, Juan Carlos, Nurlaily, Ely, Putri, Anditania Sari Dwi, Sungkono, Sungkono, Yulianto, Tri, Dewayatna, Winter
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Zdroj: AIP Conference Proceedings; 2024, Vol. 2967 Issue 1, p1-7, 7p
Abstrakt: Zr-4 alloy in the nuclear industry is used as a cladding material for PWR. In order to prepare for the fabrication and prototype of PWR fuel, PRTBBNLR has carried out irradiation tests on Zr-4 cladding material at the G.A. Siwabessy power ramp test facility. The cladding material is Zr-4 alloy in the form of a short pin. Irradiation is carried out at a power of 15 MW, the average thermal neutron flux is 1.15 x 1013 with the highest thermal neutron flux distribution 4.65 x 1013 and the lowest thermal neutron flux is 3.14 x 1010, the secondary coolant outlet temperature is 42 °C, and the pressure is in the range of 16.5-17.5 MPa for 350 hours. To determine the mechanical performance of the cladding material, it is necessary to do a post-irradiation test in a radiometallurgy installation. Post-irradiation tests that have been carried out are tensile tests and microhardness tests. Tensile strength and hardness of the cladding material is one of the mechanical properties that can change due to irradiation in the reactor. Tensile strength was observed in the transverse direction so that the sample used was a ring without a notch with a width of 3 mm, a thickness of 0.8 mm and an inner diameter of 0.9 mm. The preparation was carried out in hot cell 104 using low speed cutting. The tensile strength was tested using a Shimadzu engine with a capacity of 10 kN at R.206. The hardness of the material was tested using microhardness with a load of 500 gF in hot cell 112. The results showed that the tensile strength and hardness of the post-irradiated sample were lower than the pre-irradiated tensile strength. However, the ductility of Zr-4 material post-irradiation and pre-irradiation did not change significantly. [ABSTRACT FROM AUTHOR]
Databáze: Complementary Index