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PERILAKU TARIK DAN STRUKTUR MIKRO BAJA TAHAN KARAT AISI 304 PASCA PERLAKUAN PANAS PADA DAERAH SENSITISASI 600 – 700 °C Sungkono; Sri Ismarwanti
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 3 (2021): 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.2021.27.3.6570

Abstract

AISI 304 stainless steel is used as a structural component of the LWR type power reactors. In the manufacture of structural component, the quality of SS 304 welded joints is determined by cooling process from the austenite to sensitization temperature. The purposes of this study were to determine tensile strength, hardness and microstructure of SS 304 in the sensitization area of 600 – 700 °C. The research method was testing of the chemical composition, tensile, hardness and microstructural properties referring to ASTM. The results show that the tensile strength of SS 304 after sensitization treatment at 600 °C (30-60 minutes) and 700 °C (30-90 minutes) was relatively the same and lower than samples without heat treatment while the sample treated at 600 °C (90 minutes) was relatively the same as the sample without heat treatment. The microstructure of SS 304 consists of d-ferrite and austenite phases and chromium carbide precipitates. The quantity of precipitate at the grain boundaries decreases with increasing temperature and holding time. The hardness after sensitization treatment at 600 – 700 °C was relatively the same on the base metal, near the fracture and the fracture area. The most crack resistant was obtained on SS 304 samples with treatment at 700 °C (90 minutes).
KARAKTERISTIK DAKTILITAS SS304 YANG TEROKSIDASI PADA TEMPERATUR TINGGI Jan Setiawan; Sungkono
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 3 (2017): 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.2017.23.3.3645

Abstract

This paper shows changes in hardness, tensile strength and ductility characteristics of SS304. The SS304 was processed by heat treatment at high temperature in atmospheric environment. SS304 is a type of stainless steel with many superior properties used in industry. In this research, a pipe made of SS304 with 30 mm in diameter was cut in transversal direction at 3 mm width to be used as a sample. The samples were processed by heat treatment at 600, 800 and 1000 °C for 1 and 2 hours in atmospheric environment. After the oxidation process, the samples were cooled by natural cooling outside the furnace or quenched in water. Hardness testing and ring tensile testing were done to the high-temperature oxidized SS304. Analyses were done to study changes in hardness, tensile strength and ductility characteristics of SS304 after oxidation process. The results show that hardness escalation occurs mainly for samples that were cooled by quenching in water compared to natural cooling. The highest hardness value was observed for the sample oxidized at 1000 °C for 1 hour and cooled by quenching, where hardness value changed from 281.25 HV before oxidation to 468.00 HV after oxidation. The tensile strength of the samples, however, tend to decrease, while the ductility of some samples tends to increase. Increase in tensile strength followed by increase in ductility occurs for samples oxidized at 600 °C for 2 hours with natural cooling. The tensile strength after oxidation reaches a value of 744.04 MPa with 12.38 % elongation escalation. As a guidance for implementation, SS304 in high temperature oxidation environment should be limited by temperature of 600 °C.
PENGARUH HIDROGEN TERHADAP KEKUATAN TARIK KELONGSONG BAHAN BAKAR NUKLIR BERBASIS PADUAN ZIRKONIUM Rohmad Sigit; Fajar Al Afghani; Jan Setiawan; Sungkono
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 3 (2017): 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.2017.23.3.3648

Abstract

During reactor operation, zircaloy-4 (Zr-4) as fuel cladding is under an environment that can potentially cause mechanical failure, especially by the effect of cladding-hydrogen interaction. Hydrogen would diffuse and precipitate to form brittle hydrides when the solubility limit is surpassed. In this experiment, ring tensile test method was used to examine the effect of hydrides existence on tensile strength of Zr-4 cladding. The Zr-4 sample was annealed at 500 °C and 600 °C for an hour in vacuum condition and followed by hydriding with a pressure up to 1000 mbar with 3 hours holding time and slow cooling. According to ideal gas equation, hydrogen content in Zr-4 reaches about 674 ppm and 1215 ppm at hydriding temperature of 500 °C and 600 °C respectively. Microstructure observation shows that hydrides precipitate was formed at grain boundaries. The hydrides were found to be longer and thicker at higher hydriding temperature. As the hydrogen content increases, the ring tensile test shows increasing stress at 4.4 %, decreasing strain at 2.1 % and increasing microhardness level at 13 %. This result confirms that the existence of hydrides precipitates in cladding has an effect of increasing the tensile strength and decreasing the ductility obviously.
KARAKTERISASI LAPISAN PENYERAP DAPAT BAKAR PADA PERMUKAAN PELET UO2 + DOPAN TiO2 Sungkono; Tri Mardji Atmono
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (2016): 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.2016.22.3.3182

Abstract

Burnable absorber layer on the surface of UO2 + doped TiO2 pellets have successfully created using RF sputtering methods. The objective of this research is to obtain of microstructure characters of UO2 + doped TiO2 pellets, thickness, micro hardness, chemical composition and crystal structure of burnable absorber layer on the surface of UO2 pellets. The methods used are the microstructure and layer thickness using optical microscopy, layer hardness with micro Vickers hardness method, chemical composition by XRF spectrometry, and crystal structure by X-ray diffraction. The results showed that the larger of TiO2 content in the pellets then the greater of the grain size in the microstructure of the pellets and the thicker of the layer formed on the surface of UO2 pellets. The hardness of surface layer of UO2 + doped TiO2 sintered pellets are equal and does not depend on the dopant concentration of TiO2. The surface layer of UO2 + 0.3 % TiO2, UO2 + 0.5 % TiO2 and UO2 + 0.7 % TiO2 sintered pellets are containing zirconium respectively 1.97 mg, 2.47 mg and 4.81 mg. Burnable absorber layer on the surface of UO2 + doped TiO2 sintered pellets have ZrB2 phase with a hexagonal crystal structure.
PELAPISAN PERMUKAAN PELET UO2 DENGAN ZIRKONIUM DIBORIDA MENGGUNAKAN METODA SPUTTERING Sungkono; Tri Mardji Atmono; Dwi Priyantoro
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 1 (2016): 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.2016.22.1.2744

Abstract

Development of the nuclear fuel technology was aimed to improve nuclear power plant efficiency. One of the proposed solutions was utilization nuclear fuel with the high burn up. This leads to an increase in gas fission and nuclear reactor core reactivity. The excess reactivity of the reactor core controlled by integrated fuel burnable absorber. In connection it has made a layered thin UO2 pellets with burnable absorber. The objectives of this research was to obtain the characters of zirconium diboride layer on UO2 pellets surface i.e microstructure, crystal structure and chemical composition. The results of this experiment showed that the microstructure of UO2 + 0.4% Cr2O3 pellet has equiaxial and acicular grains with a diameter of 2.44 mm, whereas the UO2 + 0.3% Nb2O5 pellets has a grain structure in the form of equiaxial and flattened rod with a diameter of 2.47 mm. The layer of zirconium diboride on the surface of UO2 + 0.4% Cr2O3 and UO2 + 0.3% Nb2O5 pellets are similar namely thin and compact with a thickness of 2.71 mm and 2.82 mm. The identification of X-ray diffraction pattern on UO2 + 0.4% Cr2O3 and UO2 + 0.3% Nb2O5 pellets to exhibit there are of UO2 phase with cubical crystal structure and phase ZrB2 phase with hexagonal crystal structure. Meanwhile, zirconium concentration on the surface layer of UO2 + 0.4% Cr2O3 and UO2 + 0.3% Nb2O5 pellets each of 1.82 mg and 1.90 mg, the presence of zirconium element show that ZrB2 layer formed on the surface of UO2 pellets.