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All Journal Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Sungkono Sungkono
Pusat Teknologi Bahan Bakar Nuklir - BATAN
Materials Science & Nanotechnology

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PERILAKU TARIK DAN STRUKTUR MIKRO BAJA TAHAN KARAT AISI 304 PASCA PERLAKUAN PANAS PADA DAERAH SENSITISASI 600 – 700 °C Sungkono Sungkono; Sri Ismarwanti
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 27, No 3 (2021): Oktober, 2021
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.3.6570

Abstract

PERILAKU TARIK DAN STRUKTUR MIKRO BAJA TAHAN KARAT AISI 304 PASCA PERLAKUAN PANAS PADA DAERAH SENSITISASI 600 – 700 °C. Baja tahan karat AISI 304 digunakan sebagai komponen struktur reaktor daya tipe LWR. Dalam pembuatan komponen struktur, kualitas sambungan lasan SS 304 ditentukan oleh proses pendinginan dari temperatur austenit ke sensitisasi. Tujuan penelitian adalah mengetahui karakter kekuatan tarik, kekerasan dan struktur mikro SS 304 pada daerah sensitisasi 600-700 °C. Metoda penelitian yang digunakan adalah pengujian komposisi kimia, tarik, kekerasan, dan struktur mikro yang mengacu pada ASTM. Hasil penelitian menunjukkan bahwa kekuatan tarik SS 304 pasca perlakuan sensitisasi pada (600 °C, 30- 60 menit) dan (700 °C, 30-90 menit) relatif sama dan lebih rendah dibandingkan tanpa perlakuan panas, sedangkan pada (600 °C, 90 menit) relatif sama dengan sampel tanpa perlakuan panas. Struktur mikro SS 304 terdiri atas fasa ferit-d dan austenit serta presipitat khrom karbida. Kuantitas presipitat di batas butir menurun dengan bertambahnya temperatur dan waktu penahanan. Kekerasan pasca perlakuan sensitisasi pada 600 - 700°C relatif sama di base metal, dekat patahan dan daerah patahan. Ketangguhan retak terbaik diperoleh pada sampel SS 304 dengan perlakuan (700 °C, 90 menit).Kata kunci: baja tahan karat, sensitisasi, kekuatan tarik, kekerasan, struktur mikro, presipitat.
PENGARUH ARAH PENGEROLAN DAN SHEAR CUTTING TERHADAP KARAKTER PADUAN AlMg2 SEBAGAI MATERIAL CLADDING BAHAN BAKAR REAKTOR RISET Sungkono Sungkono; Sri Ismarwanti
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 26, No 3 (2020): Oktober, 2020
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2020.26.3.6090

Abstract

PENGARUH ARAH PENGEROLAN DAN SHEAR CUTTING TERHADAP KARAKTER PADUAN AlMg2 SEBAGAI MATERIAL CLADDING BAHAN BAKAR REAKTOR RISET. Proses pengerolan paduan AlMg2 dilakukan secara bertahap hingga diperoleh ketebalan tertentu dengan syarat perilaku mekanik akhir sesuai spesifikasi cladding bahan bakar reaktor riset. Pada pengujian tarik elemen bakar pasca iradiasi digunakan spesimen mini untuk meminimalkan limbah radioaktif. Tujuan penelitian adalah mendapatkan pengaruh arah pengerolan dan shear cutting terhadap karakter paduan AlMg2. Metode yang digunakan adalah pengujian tarik, metalografi dan kekerasan pada sampel pasca pengerolan dan spesimen mini paduan AlMg2. Hasil penelitian menunjukkan bahwa paduan AlMg2 searah pengerolan mempunyai kekuatan tarik dan kekerasan lebih rendah dan lebih ulet dibandingkan arah melintang pengerolan. Struktur paduan AlMg2 pasca pengerolan panas terdiri atas fasa a(Al) dan presipitat yang terdistribusi di sepanjang butir batang pipih searah pengerolan sampel. Shear cutting mempengaruhi lebar dan kekerasan daerah deformasi pada permukaan bekas potong spesimen mini.Kata kunci: arah pengerolan, shear cutting, paduan AlMg2, kekuatan tarik, kekerasan, mikrostruktur.
PEMBUATAN SERBUK U-6Zr DENGAN PENGKAYAAN URANIUM 19,75 % UNTUK BAHAN BAKAR REAKTOR RISET Masrukan Masrukan; Sungkono Sungkono; Yanlinastuti Yanlinastuti; Tri Yulianto; Ridwan Ridwan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 3 (2015): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2015.21.3.2460

Abstract

Making U-6Zr alloy powder with enrichment of 19.75 % for a research reactor fuel has been done. Making of U-6Zr fuel in order to find new fuels that have a high density to replace the existing fuel U3Si2-Al. The purpose of this experiment was to determine the properties of U-6Zr alloy powder obtained from the hydriding-dehydriding process as a candidate research reactor fuel. Initially was made U-6Zr ingot by melting U and Zr metals using electric arc melting furnace. U-6Zr ingots were found then cut into pieces and put into hydriding-dehydriding equipment that operates at pressures 14,46054 psi and hydriding temperatures of 350 oC. Ingots that out of the hydriding-dehydriding equipment becomes brittle then was crushed so becomes powder. Powder that obtained subjected to the test, including chemical composition testing, density, hydrogen content, phase and thermal properties. The results testing show that chemical composition of some elements such as Al, Ca, Cu, and Ni exceeded the permitted limit, each of which contained elements of 202.21 ppm, 214.05 ppm, 61.25 ppm, and 134.53 ppm. On testing the density obtained that U-6Zr powder density of 13.57 g/cc and the testing of hydrogen residual content obtained hydrogen residual content of 0.16 %. For the testing phase were obtained the αU and δU phases, while in testing of the transformation temperature, there are two peaks, the first peak occurs at a temperature of 274 to 311 °C and a second peak occurs at a temperature of 493 to 527 oC. The first peak occurs endothermic reaction by absorbing heat of 6.23 cal/g but not formed a new phase, while the second peak occurs exothermic reaction with brought out heat of -9.34 cal/g and formed αZr phase. Meanwhile, the heat capacity of the test at temperature of 34 to 75 °C, the decrease in the value of the heat capacity accompanied heat absorption. At higher temperatures up to 437 °C, heat capacity value becomes negative and accompanied by heat expenditure. It can be concluded that the alloy the U-6Zr when viewed from the chemical composition can still be used for fuel research reactor. Residual hydrogen still found in small quantities in the U-6Zr powder that can be eliminated by heating for longer. Reaction between Zr with residual hydrogen to form the αZ phase is accompanied exothermic reaction with brought out heat of 93 449 cal/g.
Co-Authors Masrukan Masrukan Ridwan Ridwan Sri Ismarwanti Sri Ismarwanti Tri Yulianto Yanlinastuti Yanlinastuti