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Budi Santoso; Petrus Zacharias
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2011
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2011
AbstractAbstract
[en] A pipe stress analysis with non metallic pipe has been performed. The analysis is carried out to estimate the provision of sufficient flexibility in the piping system to ensure that the heat expansion and contraction of the pipe is still in the allowable stress range. The stress analysis can be used to determine the location and type of support that will be installed. The stress calculation was carried out utilizing the CAESAR II on the static load of dead weight. operating and thermal. With performing the stress analysis, the layout of the piping system can be designed with the requirements of piping stress and pipe support. Besides, the piping system configuration must sufficiently flexible for thermal expansion, etc to commensurate with the intended service such as temperature, pressure and anticipated loading. (author)
Original Title
Analisa tegangan pipa dengan bahan pipa non metalik dalam sistem pemipaan
Primary Subject
Source
Achmad Suntoro; Wiranto Budi Santoso; Bambang Galung Susanto; Sri Mulyono Atmojo; Ari Satmoko (Badan Tenaga Nuklir Nasional (BATAN), Jakarta (Indonesia)) (eds.); Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia); 378 p; ISSN 1693-3346; ; 30 Nov 2011; p. 366-371; Scientific Engineering Meeting for Nuclear Devices; Pertemuan Ilmiah Rekayasa Perangkat Nuklir; Serpong (Indonesia); 30 Nov 2011; Also available from Directorate of Repository, Multimedia and Scientific Publishing, National Research and Innovation Agency, Kawasan Sains dan Teknologi - BRIN, KST B. J. Habibie, Gedung 120 TMC, Jl. Raya Puspiptek Serpong, Phone (+62 21) 7560009, Tangerang Selatan 15314 (ID); 4 refs.; 2 tabs.; 4 figs.
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Putut Hery Setiawan; Petrus Zacharias
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
AbstractAbstract
[en] The conversion process of UF6 to UO2 in nuclear fuel production plant through AUC performed using bubble reactor. The main product of the bubble reactor is Ammonium Uranyl Carbonate (AUC), which is accommodated by the settling tank. Bubble reactor tanks are designed consisted of a vertical-shaped shell and a head shaped torispherical. The design performed by using the standard ASME Sec. VII, Div.1. Input data from the process data sheet that contains a dimensional specification tanks, pressure, efficiency and corrosion allowance (CA). From the calculation of the shell wall thickness is 0.37 mm and a wall thickness of head is 0.65 mm. Thickness is still yet to be coupled with a corrosion allowance, for Hastelloy material in an fluid service of fluorine, CA value set at 3, 175 mm for 25 year of plant. In consideration of the thickness of the tank design is used by 4 mm. (author)
Original Title
Perhitungan tebal dan tutup tangki reaktor gelembung pabrik elemen bakar nuklir tipe PWR 1000 Mwe untuk PLTN di Indonesia
Primary Subject
Source
Wiranto Budi Santoso; Bambang Galung Susanto; Ari Satmoko (Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia); 419 p; ISSN 1693-3346; ; Nov 2013; p. 94-102; Scientific Meeting of Nuclear Devices Engineering; Pertemuan Ilmiah Perekayasaan Perangkat Nuklir; Serpong (Indonesia); 14 Nov 2013; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 6 refs.; 4 figs.
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Kukuh Prayogo; Petrus Zacharias; Krismawan
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
AbstractAbstract
[en] Activities basic design of mechanical systems plant yellow cake uranium by product of phosphoric acid plant has been done, one part of the activity is to make the routing system piping that surroundings pump area. Function of the pipe in the area of the pump is to provide a conduit for the flow of fluid into and out of the pump, without adversely affecting the performance or reliability of the pump. However a lot of pump performance and reliability problems caused or exacerbated by inadequate piping system. The purpose of the design requirements was to improve efficiency and meet the design standards that are relevant to the pump by providing the basic concepts necessary for the design of piping. With the requirements of piping system design is expected to be designed and engineered to efficiently so yellow cake plant can operate with high performance and reliable and have high economic value. (author)
Original Title
Studi persyaratan desain sistem perpipaan di area pompa untuk basic design pabrik yellow cake dari uranium hasil samping pabrik asam fosfat
Primary Subject
Source
Wiranto Budi Santoso; Bambang Galung Susanto; Ari Satmoko (Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia); 419 p; ISSN 1693-3346; ; Nov 2013; p. 103-110; Scientific Meeting of Nuclear Devices Engineering; Pertemuan Ilmiah Perekayasaan Perangkat Nuklir; Serpong (Indonesia); 14 Nov 2013; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 3 refs.; 1 tab.
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Syamsurrijal Ramdja; Petrus Zacharias
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
AbstractAbstract
[en] It has been verification of the calculations Hook Overhead Traveling Crane with a lift capacity of 25 tons of used nuclear fuel at the plant elements. Calculation verification is the examination of the correctness or suitability of the data size and dimension standards are used and whether the material used is safe for use in operating activities. This is done to determine whether the hook is still in the material strength limit allowed. Verify calculations based on applicable standards and with a conservative safety factors, to: hooks , axial bearings, latches and shackle bearers. After verification of the calculations, it was found that the hook consisting of hooks, axial bearings, hook and shackle bearer in a safe condition. (author)
Original Title
Verifikasi perhitungan perangkat Hook (kait) Overhead Travelling Crane dengan kapasitas angkat 25 ton pada pabrik elemen bakar nuklir
Primary Subject
Source
Wiranto Budi Santoso; Bambang Galung Susanto; Ari Satmoko (Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia); 419 p; ISSN 1693-3346; ; Nov 2013; p. 125-138; Scientific Meeting of Nuclear Devices Engineering; Pertemuan Ilmiah Perekayasaan Perangkat Nuklir; Serpong (Indonesia); 14 Nov 2013; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 6 refs.; 6 figs.
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AbstractAbstract
[en] Researches conducted by Batan's researchers have resulted in a number competences that can be used to produce goods and services, which will be applied to industrial sector. However, there are difficulties how to convey and utilize the R and D products into industrial sector. Evaluation results show that each research result should be completed with techno-economy analysis to obtain the feasibility of a product for industry. Further analysis on multy-product concept, in which one business can produce many main products, will be done. For this purpose, a software package simulating techno-economy I economic feasibility which uses deterministic and stochastic data (Monte Carlo method) was been carried out for multi-product including side product. The programming language used in Visual Basic Studio Net 2003 and SQL as data base processing software. This software applied sensitivity test to identify which investment criteria is sensitive for the prospective businesses. Performance test (trial test) has been conducted and the results are in line with the design requirement, such as investment feasibility and sensitivity displayed deterministically and stochastically. These result can be interpreted very well to support business decision. Validation has been performed using Microsoft Excel (for single product). The result of the trial test and validation show that this package is suitable for demands and is ready for use. (author)
Original Title
Simulasi teknoekonomi berbasis data deterministik dan stokastik untuk produk rekayasa hasil litbang BATAN
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Available from Center for Informatics and Nuclear Strategic Zone Utilization, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 5 refs.; 3 figs.
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Journal Article
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Prima (Tangerang); ISSN 1411-0296; ; v. VII(13); p. 451-456
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Petrus Zacharias; Ari Satmoko; Sutomo
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
AbstractAbstract
[en] The mechanical equipment of a gamma irradiator consists of equipment such as source rack drive mechanism, product transport mechanism, and pool liner. These equipment are a part of the irradiation facility, therefore the design should accommodate the radiation safety factors. For this purpose, design requirements have been developed with a priority of radiation safety in accordance with the regulations of BAPETEN ( No. 11/Ka.BAPETEN/VI/99 ) and the International Atomic Energy Agency (Specific Safety Guide No. SSG - 8, 2010). For the practical design needs, the design requirements improved and composed to form design requirements for functionality, performance, interfaces, design constraints, environmental conditions, and ease of maintenance. From these activities are produced the design requirements for source rack drive mechanism, for product transport mechanisms, and for pool liner. (author)
Original Title
Studi persyaratan desain bagian mekanik iradiator gamma 200 kCi
Primary Subject
Source
Wiranto Budi Santoso; Bambang Galung Susanto; Ari Satmoko (Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia); 419 p; ISSN 1693-3346; ; Nov 2013; p. 352-368; Scientific Meeting of Nuclear Devices Engineering; Pertemuan Ilmiah Perekayasaan Perangkat Nuklir; Serpong (Indonesia); 14 Nov 2013; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 6 refs.
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AbstractAbstract
[en] To keep the quality of the products to conform to established standards, there should be an inspection or examination of the products. To determine whether there is any defect in the products prior to the next process or before the products to be launched to the market, it is usually the product to be inspected by Non Destructive Testing method (NDT), which is testing the material without spoiling the material being tested. To inspect the absence of defects in the welded joints in irradiator pool liner, the radiographic examination and liquid penetrant have been conducted. The examination obtained some undercuts and porosities defects in welded joints. All of welded defects have been repaired by rewelding according to the recommendation. And all repaired weld in joints have been checked by repeating radiography and liquid penetrant examination and by repeating the original inspection procedure. (author)
Original Title
Uji tanpa rusak pada sambungan lasan liner kolam iradiator gamma
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Secondary Subject
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Available from Center for Informatics and Nuclear Strategic Zone Utilization, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 9 refs.; 1 tab.; 6 figs.
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Journal Article
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Prima (Tangerang); ISSN 1411-0296; ; v. 13(2); p. 1-11
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Budi Santoso; Petrus Zacharias, E-mail: ibed.santos@yahoo.com2012
AbstractAbstract
[en] Pipe stress analysis has been performed on the primary coolant system of the reactor TRIGA Mark II Bandung. Analysis due to the influence of internal load to the strength of the piping system. Internal loads are loads that arise due to the effects of pressure and fluid temperature. Both loads are working simultaneously and can cause stress, force and moment as well as a shift in the piping system. There fore, in designing the piping system aligned to the stress, force and moment as well as the shift that occurs does not exceed the allowable limits. From the analysis with the help of software CAESAR II shows that the stress, force, torque and the shift is still below the allowable limit. (author)
Original Title
Analisis tegangan pipa pada sistem pendingin sekunder reaktor TRIGA Mark II Bandung
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4 refs.; 3 tabs.; 2 figs.
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Journal Article
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Jurnal Perangkat Nuklir; ISSN 1978-3515; ; v. 6(1); p. 19-25
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COOLING SYSTEMS, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, THERMAL REACTORS, TRIGA TYPE REACTORS, TUBES, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Ari Satmoko; Petrus Zacharias; Sutomo; Hyundianto Arif Gunawan; Putut Hery S
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
AbstractAbstract
[en] BATAN has a program on gamma irradiator facility intended for industrial interests especially for preservative foods and agricultural products. Irradiator design is developed by referring to the irradiator category IV. To develop the concept design into detailed design, many alternatives are dispensable such as its technologies, technic or methods. Its advantages and disadvantages should be evaluated. It therefore results in only one alternative that will be developed to be the detailed design. For radioactive source loading-unloading process, the design refers practically to the existing model. To increase the radiation dose efficiency, source pencils are arranged into two thin parallel racks. Each rack consists of two stages. The product will receive an optimal radiation dose when it passes the location between both racks. SS304 wire is the best alternative for lifting racks. To avoid rotation and swing phenomena, racks are provided with guide in wire in both side of racks. These wires are equipped with tensioners and also springs to maintain its tension. The product transport mechanism has a function to make products close or far away from the radioactive source. Overhead conveyor has more advantages since its supports hanging on the ceiling offer a more free space. In order to be more efficient and economic, the products move continuously but can be stopped at certain locations. Since its discrete characteristic, the convenient conveyor type is power and free. The conveyor line is designed to around source racks and passes by the center point between both of racks in order that the radiation dose becomes optimal and evenly spread. To stop the product at certain locations, pneumatic stoppers are provided. Product loading into the conveyor and its unloading are performed automatically by providing the two stages feeder way. (author)
Original Title
Pemilihan desain mekanik pad a loading-unloading sumber radioaktif, pengangkat rak sumber dan mekanisme transportasi produk untuk iradiator gamma
Primary Subject
Source
Wiranto Budi Santoso; Bambang Galung Susanto; Ari Satmoko (Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia); 419 p; ISSN 1693-3346; ; Nov 2013; p. 324-338; Scientific Meeting of Nuclear Devices Engineering; Pertemuan Ilmiah Perekayasaan Perangkat Nuklir; Serpong (Indonesia); 14 Nov 2013; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 5 refs.; 3 figs.
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ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, ELECTROMAGNETIC RADIATION, EQUIPMENT, HAULAGE EQUIPMENT, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IONIZING RADIATIONS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MATERIALS HANDLING, MATERIALS HANDLING EQUIPMENT, NICKEL ALLOYS, RADIATIONS, STAINLESS STEELS, STEEL-CR19NI10, STEELS, TRANSITION ELEMENT ALLOYS
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Hana Subhiyah; Petrus Zacharias, E-mail: Hana.subhiyah@gmail.com, E-mail: petza@batan.go.id
Proceedings National Seminar on Nuclear Technology Utilization in Conjunction 20172017
Proceedings National Seminar on Nuclear Technology Utilization in Conjunction 20172017
AbstractAbstract
[en] The increase in national energy demand by 2050 is estimated to be still dominated by fossil fuels of 72 %. According to the National Energy Policy, new and renewable energy contributions are expected to include biomass, nuclear, hydropower, solar power, wind power by 5 % by 2025. Nuclear is one of the new energy sources to consider for meeting national energy needs. At the moment the National Nuclear Energy Agency (BATAN) is trying to design an Experimental Reactor (RDE) from a High Temperature Gas-cooled Reactor (HTGR) type reactor derivative. The helium purification system on RDE 10 MWth has an important function as a gaseous and radioactive contaminant in helium gas. Calculation of wall thickness in helium purification system at Experimental Power Plant aims to find out how thickness of pipe should be used so that there is no need for special order so it is cheaper. The calculation process is done manually in accordance with ASME B 31.3 on power piping. The results of calculations in the helium purification system show the thickness of the pipe obtained is a small pipe thickness between the schedules 5 and 10. And the thickness of the largest pipe is on schedule 40. (author)
Original Title
Perhitungan ketebalan pipa disistem purifikasi helium pada reaktor daya eksperimental 10 MWth
Primary Subject
Source
Suminar S Achmadi (Bogor Agricultural University, Bogor (Indonesia)); Agus Purwanto (STIKIP Surya, Tangerang (Indonesia)); Sutriyo (University of Indonesia, Depok (Indonesia)); Hendig Winarno; Ridwan; Rohadi Awaluddin; Imam Kambali; Achmad Suntoro; Ari Satmoko; Iwan Sumirat; Teguh Surya (National Nuclear Energy Agency, Jakarta (Indonesia)) (eds.); National Nuclear Energy Agency with Forum for Nuclear Cooperation in Asia (FNCA), Jakarta (Indonesia); 513 p; ISSN 2540-8062; ; Nov 2017; p. 408-416; Nuclear Technology Utilization in the fields of Food, Health, Industry and Environment Trough Strengthening Regional Collaboration; Pendayagunaan Teknologi Nuklir di Bidang Pangan, Kesehatan, Industri dan Lingkungan Melalui Penguatan Kerjasama Regional; Jakarta (Indonesia); 21-23 Nov 2017; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 6 refs.; 1 tab.; 2 figs.
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