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Studi Perbandingan tentang Sifat Mekanik dan Struktur Mikro Material Radiator Impor dan Material Radiator Lokal Rahmad Rahmad; Usman Sudjadi
JMPM (Jurnal Material dan Proses Manufaktur) Vol 5, No 1 (2021): Juni
Publisher : Universitas Muhammadiyah Yogyakarta

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.18196/jmpm.v5i1.12040

Abstract

Pengujian pada studi ini menggunakan sampel core radiator impor dan core radiator lokal. Metode pengujian dilakukan dengan tiga tahapan yaitu sebelum heat treatment, sesudah heat treatment, dan uji korosi dengan direndam cairan yang berbeda yaitu H2SO4, NAOH, dan cairan radiator selama 15 hari. Sebelum heat treatment, dilakukan uji komposisi kimia semua sampel radiator dengan alat XRF, uji struktur mikro dengan mikroskop optik pembesaran 500x, dan uji kekerasan micro-vickers dengan beban 100gf dalam waktu 10 detik. Heat treatment dilakukan dengan suhu 850oc dalam waktu 3 jam, kemudian direndam dengan cairan kimia selama 15 hari. Dari pengujian tersebut didapat hasil uji struktur mikro baik sebelum maupun sesudah heat treatment pada kedua sampel radiator tidak terlihat kumpulan atom, matrix dan batas butirnya. Uji kekerasan pada sampel core radiator Mercedez sebelum dipanaskan sebesar 43,4 HV dan 39,2 HV sesudah heat treatment. Pada core radiator lokal, sebelum dipanaskan sebesar43,5 HV dan 38,2 HV sesudah dipanaskan. Hasil uji komposisi kimia menunjukan pada sampel core Mercedez didominasi unsur Ca, Mn, dan Fe dan pada sampel core radiator lokal didominasi unsur Ca, Cu dan Zn. Hasil pengamatan dan analisa setelah direndam cairan H2S04, NAOH, dan cairan radiator pada kedua sampel menunjukkan terjadinya perubahan warna karena adanya perubahan unsur akibat peningkatan konsentrasi atom.
MECHANICAL STUDY OF 9CR-316SS-1MO FOR NUCLEAR POWER REACTOR FUEL CLADDING MATERIALS Mayda Purnama; Usman Sudjadi
International Journal of Innovation in Mechanical Engineering and Advanced Materials Vol 4, No 2 (2022)
Publisher : Universitas Mercu Buana, Prodi S2 Teknik Mesin

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.22441/ijimeam.v4i2.16832

Abstract

Cladding or cladding used for nuclear fuel elements requires special requirements such as good mechanical properties, radiation resistance, corrosion resistance, adequate physical and chemical properties, and low thermal neutron absorption. Materials that are widely used as structural materials for nuclear reactors are beryllium, magnesium, aluminum, zirconium and their alloys. Alloy 9Cr-316-1Mo as Nuclear fuel cladding material. 9Cr-316-1Mo material has been made. The material 9Cr-316-1Mo was chosen as an alternative cladding material because it has good mechanical and chemical properties with a microscopic cross-section of 2.6 barn. At first, the 9Cr-316-1Mo sample was cast withThe composition is 90% 316L Stainless Steel, 9% Chromium (Cr) and 1% Molybdenum (Mo) is added using an electric arc. After casting the alloy,the composition of 9Cr-316-1Mo was tested without heating and then given heat treatment (tempering) starting from 100 0C, 200 0C, 300 0C, 400 0C and 500 0C and allowed to stand for 60 minutes, then tested for hardness (rockwell) , Impact testing, micro structure testing and Chemical composition testing (XRF). The results of the Rockwell hardness test obtained the highest hardness value in the sample without tempering, namely 20.66 HRc and the lowest hardness value in the sample with tempering 500 0C, namely 16.33 HRc. Then the impact test results obtained the highest impact energy value in the sample with tempering 100 0C, which is 0.9996 Joule/mm2 and the lowest impact energy value in the sample with tempering 500 0C, which is 0.9962 Joule/mm2. The results of the microstructure test showed that the structure of 9Cr-316-1Mo still contained ferrite, pearlite and martensite. The testing process is still not fully completed and will be reported later.