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AbstractAbstract
[en] According to International Desalination Association 2009, there are 14,400 desalination installations in the world which produced 59.9 million m"3 per day and it was estimated to be increase continuously about 12,3% per year. Generally, fossil fuel has used as heat source which its combustion process will emit of CO_2 gas and another greenhouse gases. Increasing of fossil fuel utilization as energy process source, in : large scale desalination plant is not sustainable long-term option in term of environmental impact viewpoint. Nuclear Power Plant (NPP) is one of energy source which can produce large scale energy and it is also potential for cogeneration purposes which it produce electricity, as well as nuclear heat is also used for heat process, such as : desalination. Among all NPP type, PWR is the most utilized. In the heat utilization of PWR type NPP for desalination is needed a steam source selection of NPP secondary cycle. The exact selection of steam extraction point will be resulting an optimum cogeneration system to fulfil heat requirement for desalination by reduction of electricity as minimal as possible. Basically, there are 4 scheme scenario which are based on 2 steam extraction points, namely cross pipe and extraction line. Optimization is conducted by using Cycle Tempo Programme. Result of this study showed that third scheme of crossover pipe of steam extraction point is the best scheme with 1,039.1 MWe of power, 34.5 MWe of internal electricity needs and 149 MWe of power loss by cogeneration system and 1,004.6 MWe of transmission power. (author)
Original Title
Identifikasi skema optimum ekstrasi uap untuk instalasi desalinasi pada sistem kogenerasi PLTN PWR
Primary Subject
Source
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); 7 refs., 2 tabs., 8 figs.
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Journal Article
Journal
Jurnal Pengembangan Energi Nuklir; ISSN 1410-9816; ; v. 13(1); p. 9-18
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AbstractAbstract
[en] EOR is a method used to increasing oil recovery by injecting material or other to the reservoir. There are 3 EOR technique have been used in the world, namely thermal injection, chemical injection dan Miscible. Thermal injection method is the method most widely used in the world, however, one drawback is the loss of heat during steam distribution to the injection wells. In Indonesia, EOR application has been successfully done in the field of Duri, Chevron uses steam injection method, but still use petroleum as a fuel for steam production. In order to save oil reserves, it was done the introduction of co-generation nuclear power plants to supply some of the heat of nuclear power plants for EOR processes. In cogeneration nuclear power plant, the safety aspect is main priority. The purpose of the study was to evaluate the distance NPP with oil wells by considering heat loss and safety aspects. The method of study and calculations done using Tempo Cycle program. The study results showed that in the distance of 400 meter as exclusion zone of PBMR reactor, with pipe insulation thickness 1 in, the amount of heat loss of 277, 883 kw, while in pipe isolation thickness 2 in, amount of heat loss became 162,634 kw and with isolation thickness 3 in, amount of heat loss 120,767 kw., heat loss can be overcome and provide insulation pipes and improve the quality of saturated steam into superheated. (author)
Original Title
Penentuan jarak PLTN dengan sumur minyak untuk Enhanced Oil Recovery (EOR) ditinjau dari aspek kehilangan panas dan keselamatan
Primary Subject
Source
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); 16 refs., 2 tabs., 4 figs.
Record Type
Journal Article
Journal
Jurnal Pengembangan Energi Nuklir; ISSN 1410-9816; ; v. 15(2); p. 127-137
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Dedy Priambodo, E-mail: dedypriambodo@batan.go.id
Proceedings of the National Seminar on Nuclear Energy Infrastructure2018
Proceedings of the National Seminar on Nuclear Energy Infrastructure2018
AbstractAbstract
[en] The experimental Power Reactor (RDE) is BATAN's flagship program as an initial step in Indonesia's future reactor design. RDE as an experimental reactor is designed to be able to produce electricity and heat for industrial processes. This paper aims to serve as a reference for the commercial development of RDE. The industrial model taken in this study was a utility unit at the East Kalimantan Fertilizer Factory (PKT) or called Factory 6. The study began with the identification of utility needs supplied by Factory 6 and then simulated on the RDE system. From this study, the utility requirements supplied by Factory 6 are high pressure steam 500 °C/85 bar, 131 kg/s and electricity of 60 MWe. This need can be fulfilled by increasing the RDE reactor power to 550 MWt and the output pressure of the steam generator to 85 bar and also creating a tie in to extract high pressure steam from the steam generator outlet line. (author)
Original Title
Pengembangan reaktor daya eksperimental sebagai unit utilitas pabrik
Primary Subject
Source
Sugiman; Mirmanto (Universitas Mataram (UNRAM), Nusa Tenggara Barat (Indonesia)) (eds.); Retno Gumilang Dewi (ed.) (Institut Teknologi Bandung (ITB), Bandung (Indonesia)); Eko Budi Lelono (ed.) (Lembaga Minyak dan Gas (LEMIGAS), Jakarta (Indonesia)); Heni Susiati; Sahala Maruli Lumban Raja; Edwaren Liun; Erlan Dewita; Wiku Lulus Widodo; Sunarko; Imam Bastori; Tagor Malem Sembiring; Susetyo Trijoko; Nuryanti; Dharu Dewi; Yuliastuti (BATAN, Jakarta (Indonesia)) (eds.); Center for Nuclear Energy Systems, National Nuclear Energy Agency, Jakarta (Indonesia); [520 p.]; ISSN 2621-3125; ; Oct 2018; 7 p; National Seminar on Nuclear Energy Infrastructure; Seminar Nasional Infrastruktur Energi Nuklir; Yogyakarta (Indonesia); 25 Oct 2018; 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); 32 refs.; 4 tabs.; 3 figs.
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Denissa Beauty Syahna; Sunarko; Dedy Priambodo; Imam Hamzah, E-mail: denissabs@batan.go.id
Proceedings of the National Seminar on Nuclear Energy Infrastructure2019
Proceedings of the National Seminar on Nuclear Energy Infrastructure2019
AbstractAbstract
[en] Meteorological monitoring on the site of Nuclear Power Plant (NPP) has been conducted in West Bangka and South Bangka. The parameters monitored include air temperature, wind direction, wind speed, humidity, air pressure, solar radiation and rainfall. Another important parameter which is not directly monitored using sensors is atmospheric stability. Atmospheric stability classification assessment was determined through lapse rate method from data of air temperature in West Bangka and South Bangka in 2015 - 2016. Lapse rate method uses the rate of change temperature at levels of 10 and 60 meters. The result of lapse rate are used to determine the value of atmospheric stability classification. In this study, the determination of atmospheric stability classification uses the Pasquill stability classes. The result of atmospheric stability classification on NPP site in Bangka are dominant in class E, which is slightly stable. (author)
Original Title
Kajian kelas stabilitas udara pada tapak PLTN di pulau Bangka
Primary Subject
Source
Eka Priadi; Rudy Gianto; Slamet Widodo; Hardiansyah; Elvira; Herry Sujaini; Aji Ali Akbar; Nurhayati; Henny Herawati; Rizki Purnaini; Bomo Wibowo Sanjaya; Mohammad Sofitra; Seno Darmawan Panjaitan; Ayong Hiendro; Budhi Purwoko; Dian Rahayu Jati (Universitas Tanjungpura (UNTAN), Pontianak, Kalimantan Barat (Indonesia)) (eds.); Retno Gumilang Dewi (ed.) (Institut Teknologi Bandung (ITB), Bandung (Indonesia)); Eko Budi Lelono (ed.) (Lembaga Minyak dan Gas (LEMIGAS), Jakarta (Indonesia)); Heni Susiati; Sriyana; Edwaren Liun; Moch Djoko Birmano; Wiku Lulus Widodo; Sunarko; Imam Bastori; Tagor Malem Sembiring; Susetyo Trijoko; Nuryanti; Dharu Dewi; Yuliastuti; Mudjiono (Badan Tenaga Nuklir Nasional, Jakarta (Indonesia)) (eds.); Center for Nuclear Energy Systems, National Nuclear Energy Agency, Jakarta (Indonesia); 547 p; ISSN 2621-3125; ; Oct 2019; p. 151-156; National Seminar on Nuclear Energy Infrastructure; Seminar Nasional Infrastruktur Energi Nuklir; Pontianak (Indonesia); 10 Oct 2019; 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); 15 refs.; 3 tabs.; 4 figs.
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Dedy Priambodo; Erlan Dewita; Sudi Ariyanto, E-mail: dedypriambodo@batan.go.id2012
AbstractAbstract
[en] Hydrogen has a high potent for new energy, because of it availability. Steam reforming is a fully developed commercial technology and is the most economical method for production of hydrogen. Steam reforming uses an external source of hot gas to heat tubes in which a catalytic reaction takes place that converts steam and lighter hydrocarbons such as natural gas (methane) or refinery feedstock into hydrogen and carbon monoxide (syngas) at high temperature on primary reformer (800-900°C). Utilization of helium from HTGR as heating medium for primary reformer has consequence to type and shape of its reactor. The main goal of this paper is to determine type/shape and pre elementary design of chemical reactor for the cogeneration system of Hydrogen Plant and HTGR The primary reformer for this system is Fixed Bed Multitube reactor with specification tube: NPS 3,5 Sch 40 ST 40S, 0.281 in thickness, number of tube 849 pieces and ASTM HH 30 for tube material. Tube arrangement is 'triangular pitch' on shell Split-Ring Floating Head from Steel Alloy SA 301 Grade B equipted with 8 baffles. (author)
Original Title
Pra-rancangan primary reformer pada pabrik hidrogen yang dikopel dengan PLTN HTGR
Primary Subject
Source
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); 10 refs.; 4 tabs.; 5 figs.
Record Type
Journal Article
Journal
Jurnal Pengembangan Energi Nuklir; ISSN 1410-9816; ; v. XIV(2); p. 95-106
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ALLOYS, CARBON ADDITIONS, CARBON COMPOUNDS, CARBON OXIDES, CHALCOGENIDES, CHEMICAL REACTIONS, ECONOMICS, ELEMENTS, FLUIDS, GAS COOLED REACTORS, GASES, GRAPHITE MODERATED REACTORS, IRON ALLOYS, IRON BASE ALLOYS, NONMETALS, OXIDES, OXYGEN COMPOUNDS, POWER GENERATION, RARE GASES, REACTORS, REFORMER PROCESSES, STEAM GENERATION, STEELS, TEMPERATURE RANGE, TRANSITION ELEMENT ALLOYS
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AbstractAbstract
[en] The Screening Distance Value, SDV for each type of hazard source must be determined using a conservative approach so that the influence of the interactions event that are beyond this distance will be ignored. From observations, the most immovable sources around the site are the Petrol station (SPBU) and the LPG Station (SPPBE). Therefore, the objective of this study is to determine the SDV of SPBU and SPPBE for explosion and fire scenarios at the the Experimental Power Reactor site (RDE), Serpong Puspiptek. In this study, the Area Location of Hazardous Atmospheres (ALOHA) software was chosen to simulate the threat zone of explosion and fire from the substances of Gasoline and LPG. This simulation involves explosions and fires of iso-octane at gas stations and butane in SPPBE to analyze threat zones from accident scenarios. It is known that SDV is very dependent on the type and capacity of hazardous materials, accident scenarios and atmospheric conditions on the source of the hazard. From this study, also known a source of danger can have SDV of more than one value. SDV gas stations with a capacity of 170,000 liters for fire scenarios are 976 m and 1,200 m, while for explosion scenarios are 958 m and 1,200 m. SDV SPPBE with a capacity of 25,000 kg for the fire scenario are 445 m and 565 m, while for the explosion scenario are 430 m and 573 m. While SDV SPPBE has a capacity of 100,000 kg for the fire scenario are 913 m and 1,100 m, while for the explosion scenario are 758 m and 1,100 m. This study can provide an alternative determination of SDV for nuclear reactor site study and evaluation. (author)
Original Title
Penentuan nilai jarak aman sumber tidak bergerak: Skenario kebakaran dan ledakan pada SPBU dan SPPBE di sekitar tapak RDE
Primary Subject
Source
16 refs.; 4 tabs.; 3 figs.
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Journal Article
Journal
Jurnal Pengembangan Energi Nuklir; ISSN 1410-9816; ; v. 20(1); p. 9-16
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Dedy Priambodo; Siti Alimah; Erlan Dewita, E-mail: dedypriambodo@gmail.com2009
AbstractAbstract
[en] OPR 1000 adopts demineralization method based on ion exchanger resin and AP 1000 adopt the method that based on Reverse Osmosis (RO)-Electrodeionization (EDI). The Ion exchange process is a reversible chemical reaction of a solution and an insoluble solid. Ion exchanger use resin as polluter ions capture and will be regenerated after its saturated. RO is method using pressure to force a solution through a membrane, retaining the solute on one side and allowing the pure solvent to pass to the other side. Whereas, EDI is a combination of ion exchange and electrodialysis. The ions is taken by ion exchange resin, and then it is discharged utilizing electric potential difference. Due to water splitting phenomena in EDI, make resin will never be saturated, so the RO-EDI process is water demineralization system that use little chemical, more simple installation, capable to maintain demineralization water product quality and environmental friendly. Thereby, The RO-EDI water demineralization system is more advance then ion exchange technology. (author)
Original Title
Studi Banding Sistem Demineralisasi Air pada PLTN OPR 1000 dan AP 1000
Primary Subject
Source
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); 6 refs.; 2 tabs.; 3 figs.
Record Type
Journal Article
Journal
Jurnal Pengembangan Energi Nuklir; ISSN 1410-9816; ; v. 11(2); p. 83-91
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Dedy Priambodo; Erlan Dewita; Ign Djoko lrianto, E-mail: dedypriambodo@gmail.com2015
AbstractAbstract
[en] HTGR type reactor is planned to be built reactors as the first Experimental Power Reactor (RDE) in Indonesia. HTGR type reactor is a reactor with a high reactor outlet temperature (∽ 900 °C), high thermal efficiency and also it have inherent and passive safety systems. To determine the accuracy of the efficiency of a power plant is not enough if it merely refers to the energy efficiency just as it is based on the first law of thermodynamics, but it needs to be combined with exergy approach that is based on the second law of thermodynamics. Therefore, the purpose of the study is to analyze the energy and exergy of HTGR-steam turbine cycle system to determine the loss / heat loss that occurs in the power system components, so it can be seen the potential loss and can be repaired. The methodology used is a calculation using the program cycle due to the data input of the HTR-10 reactor. The results of analysis and evaluation of the irreversibility of HTGR reactor system using a steam turbine cycle shows that the reactor is a component of the least efficient, 61.8 % irreversibility, among all components in the system. This is due to the irreversibility of energy transfer that occurs in the cleavage reaction proceeds to the helium coolant. Steam generators, turbines, condensers, is a component of the next largest contributor loss. The study shows that the efficiency of the steam turbine cycle HTGR system has great potential to be improved so it can provide a significant effect on the improvement of the efficiency of the system. (author)
Original Title
Analisis energi dan eksergi pada sistem HTGR siklus turbin uap
Primary Subject
Source
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); 10 refs.; 3 tabs.; 5 figs.
Record Type
Journal Article
Journal
Jurnal Pengembangan Energi Nuklir; ISSN 1410-9816; ; v. XVII(1); p. 33-43
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AbstractAbstract
[en] Cogeneration NPP is potential to be applied in areas with water and electricity deficit through coupling of NPP and desalination installation (nuclear desalination). Nowadays, there are several nuclear desalination that are commercially in operation and using several nuclear reactor types as heat source, such as: LWR (PWR dan BWR), LWR (PWR dan BWR), although there is also possibility the use of other reactor types, such as: HTGR, HWR and others. The desalination technology has already commercially operated and in the large-scale production, namely: multi-stage flash (MSF) and multi-effect distillation (MED) for thermal process, reverse osmosis (RO) for membrane process, and hybrid technologies, such as: MED-RO, MSF-RO and MED-RO-TVC. In order to analyze configurations for coupling system of NPP and desalination installation in order to get optimum water cost (lowest cost) by considering economic, safety and technology aspects. Study is done by comparing several coupling configurations: PWR-RO, PWR-MED, PWR-MSF, PWR-MED-RO, PWR-MSF-RO, PWR-MED-RO-TVC, HTGR-RO, HTGR-MED, HTGR-MSF, HTGR-MED-RO, HTGR-MSF-RO, HTGR-MED-RO-TVC. Simulation is done by using DEEP-4 programme, thermal power reactor: 330 MWth, water production capacity 40.000 m3/day, seawater temperature 28.9°C, TDS 30.000 ppm and discount rate 10%. The result showed that water cost of HTGR-MED-RO coupling configuration is lower than another coupling configurations. (author)
Original Title
Analisis konfigurasi sistem kopling PLTN dan instalasi desalinasi berbasis perhitungan ekonomi
Primary Subject
Source
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); 6 refs., 8 figs.
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Journal Article
Journal
Jurnal Pengembangan Energi Nuklir; ISSN 1410-9816; ; v. 13(2); p. 111-121
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Mudjiono; Siti Alimah; Edwaren Liun; Dedy Priambodo; Adhi Nugraha, E-mail: mudzi@batan.go.id
Proceedings of the National Seminar on Nuclear Energy Infrastructure2019
Proceedings of the National Seminar on Nuclear Energy Infrastructure2019
AbstractAbstract
[en] Public policy is a series of interrelated choices made by government agencies or officials in fields involving governmental tasks, such as defense of security, energy, health, education, public welfare, crime, urban areas and others. Taking a policy cannot be separated from the involvement of stake holders. The Nuclear Power Plant (NPP) development plan in West Kalimantan is a public policy of interest and the consequences are inseparable from the involvement of stake holders. The acceptance and relevance of stake holders is not important in building infrastructure. Besides community acceptance and decision making. The study of stake holder acceptance of the planned nuclear power plant construction in West Kalimantan was agreed to be carried out on the basis of media coverage both online and offline. The distribution of stake holder statements in the media will be seen in January 2017 to August 2019. The aim of the study is to determine the level of stake holder acceptance of the planned nuclear-based nuclear power plant development in West Kalimantan. The method used is to examine and analyze consenting stake holders in the media. The study results obtained that stake holder acceptance monitored in the media showed a positive tendency of 93.67 % and negative 6.33 % towards the planned construction of the NPP in West Kalimantan. (author)
Original Title
Studi keberterimaan stakeholder berbasis media terhadap rencana pembangunan PLTN di Kalimantan Barat
Primary Subject
Source
Eka Priadi; Rudy Gianto; Slamet Widodo; Hardiansyah; Elvira; Herry Sujaini; Aji Ali Akbar; Nurhayati; Henny Herawati; Rizki Purnaini; Bomo Wibowo Sanjaya; Mohammad Sofitra; Seno Darmawan Panjaitan; Ayong Hiendro; Budhi Purwoko; Dian Rahayu Jati (Universitas Tanjungpura (UNTAN), Pontianak, Kalimantan Barat (Indonesia)) (eds.); Retno Gumilang Dewi (ed.) (Institut Teknologi Bandung (ITB), Bandung (Indonesia)); Eko Budi Lelono (ed.) (Lembaga Minyak dan Gas (LEMIGAS), Jakarta (Indonesia)); Heni Susiati; Sriyana; Edwaren Liun; Moch Djoko Birmano; Wiku Lulus Widodo; Sunarko; Imam Bastori; Tagor Malem Sembiring; Susetyo Trijoko; Nuryanti; Dharu Dewi; Yuliastuti; Mudjiono (Badan Tenaga Nuklir Nasional, Jakarta (Indonesia)) (eds.); Center for Nuclear Energy Systems, National Nuclear Energy Agency, Jakarta (Indonesia); 547 p; ISSN 2621-3125; ; Oct 2019; p. 413-418; National Seminar on Nuclear Energy Infrastructure; Seminar Nasional Infrastruktur Energi Nuklir; Pontianak (Indonesia); 10 Oct 2019; 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); 42 refs.; 2 tabs.; 1 fig.
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