Liquid Lead-Bismuth Eutectic (LBE) is a coolant of one of main candidates for the future nuclear ... more Liquid Lead-Bismuth Eutectic (LBE) is a coolant of one of main candidates for the future nuclear reactor in the world (Generation IV reactors) i.e. LFR (Lead alloy-cooled Fast Reactor), and also a spallation target material for ADS (Accelerator Driven Transmutation System). The liquid has several advantages from neutronic, thermal-hydraulic, and inert characteristic with water and air. Nevertheless, the liquid LBE has the corrosive characteristic to metals as constituent materials of fuel cladding and structural of the reactors. Therefore, development of fuel cladding and structural materials in lead-bismuth eutectic environment is one of key issues for the deployment of LFR and ADS. A zirconium alloy material i.e. ZrNbMoGe has been developed in the Center for Technology of Nuclear IndustryMaterials (PTBIN)-BATAN. In order to explore the characteristics of the zircaloy, investigation of compatibility of ZrNbMoGe in liquid LBE has been done using COSTA apparatus facility at Pulsed Po...
The Department for Pulsed Power Technology is focusing on research and development of pulsed powe... more The Department for Pulsed Power Technology is focusing on research and development of pulsed power technologies and related applications. The applications involves the electroporation of biological cells for extraction of cell contents (PEF- process), dewatering and drying of green biomass, pre-treatment of micro algae for energetic use and sustainable reduction of bacteria in contaminated effluents. Another key research topic is devoted to the development of corrosion barriers and materials for improved compatibility of structural materials in contact with liquid metal coolants. This year's report focuses primarily on the activities and results of ongoing third-party funded projects of the department.
Abstract Two MAX-phase materials, Ti 3 SiC and Ti 2 AlC, were tested at 550 °C, 650 °C and 700 °C... more Abstract Two MAX-phase materials, Ti 3 SiC and Ti 2 AlC, were tested at 550 °C, 650 °C and 700 °C up to 10 000 h in LBE (lead-bismuth-eutectic) containing of 10 −6 and 10 −8 wt% oxygen. It was found that secondary phases have a strong influence on corrosion effects. Ti 3 SiC showed a surface disintegration at 550°C/10 −6 wt% oxygen after longer exposure, while a 4–7 μm thick TiO 2 layer with Pb-Bi inclusions was detected on Ti 2 AlC. However, Ti 3 SiC is protected by a double layered oxide with an outer part of TiO 2 and a mixed inner layer of SiO 2 and TiO 2 at the higher temperatures. Ti 2 AlC formed a TiO 2 surface layer containing Al 2 O 3 . Some defects could be observed on the Ti 3 SiC surface in LBE containing 10 −8 wt% oxygen at 550 °C and 650 °C. The secondary phases between the Ti 3 SiC grains showed strong oxidation at 700 °C. Due to the high Al solubility in LBE, Ti 2 AlC experienced strong dissolution attack after longer exposure times at 650 and 700 °C.
KOMPATIBILITAS PADUAN ZIRKONIUM PAD ACAIRAN LOGAM BERAT LEAD-BISMUTH EUTECTIC . Cairan Lead Bismu... more KOMPATIBILITAS PADUAN ZIRKONIUM PAD ACAIRAN LOGAM BERAT LEAD-BISMUTH EUTECTIC . Cairan Lead Bismuth Eutectic (LBE) merupakan pendingin salah satu kandidat utama reaktor masa depan di dunia (Generation IV reactors) yaitu Lead alloy-cooled Fast Reactor (LFR) sekaligusmerupakan material target spalasi untuk Accelerator Driven Transmutation System (ADS). Cairan ini memiliki berbagai keunggulan dari segi netronik, termalhidrolik maupun sifat yang inert terhadap air dan udara. Namun cairan LBE ini bersifat korosif pada logam-logam yang menjadi penyusun material kelongsong bahan bakar dan struktur reaktor. Oleh karena itu pengembangan material kelongsong bahan bakar dan struktur reaktor dalamlingkungan LBE merupakan salah satu kunci utama dalam pengembangan LFR dan ADS. Telah dikembangkan paduan zirkonium yaitu ZrNbMoGe di Pusat Teknologi Bahan Industri Nuklir (PTBIN)-BATAN. Dalam rangka untuk mengeksplorasi karakteristik paduan zirkonium ini dilakukan investigasi kompatibilitas bahan padu...
Liquid Lead-Bismuth Eutectic (LBE) is a coolant of one of main candidates for the future nuclear ... more Liquid Lead-Bismuth Eutectic (LBE) is a coolant of one of main candidates for the future nuclear reactor in the world (Generation IV reactors) i.e. LFR (Lead alloy-cooled Fast Reactor), and also a spallation target material for ADS (Accelerator Driven Transmutation System). The liquid has several advantages from neutronic, thermal-hydraulic, and inert characteristic with water and air. Nevertheless, the liquid LBE has the corrosive characteristic to metals as constituent materials of fuel cladding and structural of the reactors. Therefore, development of fuel cladding and structural materials in lead-bismuth eutectic environment is one of key issues for the deployment of LFR and ADS. A zirconium alloy material i.e. ZrNbMoGe has been developed in the Center for Technology of Nuclear IndustryMaterials (PTBIN)-BATAN. In order to explore the characteristics of the zircaloy, investigation of compatibility of ZrNbMoGe in liquid LBE has been done using COSTA apparatus facility at Pulsed Po...
The Department for Pulsed Power Technology is focusing on research and development of pulsed powe... more The Department for Pulsed Power Technology is focusing on research and development of pulsed power technologies and related applications. The applications involves the electroporation of biological cells for extraction of cell contents (PEF- process), dewatering and drying of green biomass, pre-treatment of micro algae for energetic use and sustainable reduction of bacteria in contaminated effluents. Another key research topic is devoted to the development of corrosion barriers and materials for improved compatibility of structural materials in contact with liquid metal coolants. This year's report focuses primarily on the activities and results of ongoing third-party funded projects of the department.
Abstract Two MAX-phase materials, Ti 3 SiC and Ti 2 AlC, were tested at 550 °C, 650 °C and 700 °C... more Abstract Two MAX-phase materials, Ti 3 SiC and Ti 2 AlC, were tested at 550 °C, 650 °C and 700 °C up to 10 000 h in LBE (lead-bismuth-eutectic) containing of 10 −6 and 10 −8 wt% oxygen. It was found that secondary phases have a strong influence on corrosion effects. Ti 3 SiC showed a surface disintegration at 550°C/10 −6 wt% oxygen after longer exposure, while a 4–7 μm thick TiO 2 layer with Pb-Bi inclusions was detected on Ti 2 AlC. However, Ti 3 SiC is protected by a double layered oxide with an outer part of TiO 2 and a mixed inner layer of SiO 2 and TiO 2 at the higher temperatures. Ti 2 AlC formed a TiO 2 surface layer containing Al 2 O 3 . Some defects could be observed on the Ti 3 SiC surface in LBE containing 10 −8 wt% oxygen at 550 °C and 650 °C. The secondary phases between the Ti 3 SiC grains showed strong oxidation at 700 °C. Due to the high Al solubility in LBE, Ti 2 AlC experienced strong dissolution attack after longer exposure times at 650 and 700 °C.
KOMPATIBILITAS PADUAN ZIRKONIUM PAD ACAIRAN LOGAM BERAT LEAD-BISMUTH EUTECTIC . Cairan Lead Bismu... more KOMPATIBILITAS PADUAN ZIRKONIUM PAD ACAIRAN LOGAM BERAT LEAD-BISMUTH EUTECTIC . Cairan Lead Bismuth Eutectic (LBE) merupakan pendingin salah satu kandidat utama reaktor masa depan di dunia (Generation IV reactors) yaitu Lead alloy-cooled Fast Reactor (LFR) sekaligusmerupakan material target spalasi untuk Accelerator Driven Transmutation System (ADS). Cairan ini memiliki berbagai keunggulan dari segi netronik, termalhidrolik maupun sifat yang inert terhadap air dan udara. Namun cairan LBE ini bersifat korosif pada logam-logam yang menjadi penyusun material kelongsong bahan bakar dan struktur reaktor. Oleh karena itu pengembangan material kelongsong bahan bakar dan struktur reaktor dalamlingkungan LBE merupakan salah satu kunci utama dalam pengembangan LFR dan ADS. Telah dikembangkan paduan zirkonium yaitu ZrNbMoGe di Pusat Teknologi Bahan Industri Nuklir (PTBIN)-BATAN. Dalam rangka untuk mengeksplorasi karakteristik paduan zirkonium ini dilakukan investigasi kompatibilitas bahan padu...
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