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All Journal SIGMA EPSILON - Majalah Ilmiah Teknologi Keselamatan Nuklir Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega JPM17: Jurnal Pengabdian Masyarakat Business and Finance Journal
Hendro Tjahjono
Center for Technology Reactor and Nuclear Safety, BATAN
Arts Humanities Computer Science & IT Economics, Econometrics & Finance Energy Materials Science & Nanotechnology Social Sciences

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ANALYSIS OF THE EFFECT OF ELEVATION DIFFERENCE BETWEEN HEATER AND COOLER POSITION IN THE FASSIP-01 TEST LOOP USING RELAP5 Andi Sofrany Ekariansyah; Hendro Tjahjono; Mulya Juarsa; Surip Widodo
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 19, No 1 (2015): Februari 2015
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1072.747 KB) | DOI: 10.17146/sigma.2015.19.1.2895

Abstract

To understand the natural circulation phenomena on the passive residual heat removal system (PRHRS), development of a test section describing that phenomena in particular in the one phase condition is required. That test facility is named as FASSIP-01 in form of a vertically closed loop consisting of piping compo-nents, one cylinder tank featured with heater elements and one cooler. The heater tank will work as the heat source, and the cooler as the heat sink. This research is intended to support the experimental activity of the FASSIP-01 by conducting a simulation using the RELAP5/SCDAP/Mod3.4. Beside the standard loop configuration, the simulation is also conducted by varying the elevation of heater and cooler position to evaluate the best position resulting in the most optimal natural circulation. The results will be used as the comparison with the later performed experiment. The simulation result shows that for the case where the heater position is at the same level with the cooler position, the temperature distribution of the water after the heater and after the cooler are higher than the other two position. Looking at the natural circulation, that position results in the lowest mass flow. The position with the heater below the cooler will result in the best mass flow. On that position, only an optimiza-tion in the heat transfer surface area is needed to increase the heat transfer coefficient and secondary mass flow to remove the heat are needed to obtain more optimal performance of the water circulation caused by the density difference in the FASSIP-01 test loop.
PENGARUH DEBIT ALIRAN AIR SISI PRIMER UNTAI UJI BETA TERHADAP EFEKTIVITAS ALAT PENUKAR KALOR Suhendra Suhendra; Mulya Juarsa; Muhammad Hadi Kusuma; Hendro Tjahjono; Yogi Sirodz Gaos; Gregorius Bambang Heru
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 16, No 1 (2012): Februari 2012
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (320.258 KB) | DOI: 10.17146/sigma.2012.16.1.2898

Abstract

Telah dilakukkan analisis perubahan alat penukar kalor pada fasilitas Untai UjiBETA. Fasilitas Untai Uji BETA merupakan fasisilitas eksperimen untuk menginvestigasi fenomena thermohidrolikbaik dalam keadaan transien (kecelakaan) ataupun dalam keadaan tunak (operasi normal) sebagaisimulasi sistem pendingin. Adapun komponen dari untai uji BETA terdiri dari pre-heater, pompa primer dansekunder, alat penukar kalor, reservoir tank dan cooling tower. untuk meningkatkan performa alat penukarkalor yang terdapat di UUB adalah dengan cara mengganti alat penukar kalor tersebut. Dengan pergantian alatpenukar kalor maka perlu dilakukan karakterisasi untuk mengetahui performa alat tersebut. Eksperimen ini dilakukan dengan memvariasikan 3 macam debit aliran pada sisi primer, yaitu : 0,377 L/s, 0,472 L/s dan 0,567 L/s adapun untuk debit aliran pada sisi sekunder di beri nilai konstan, yaitu : 1,07 L/s dengan temperatur air60oC . Eksperimen karakterisasi di fokuskan untuk memperoleh hasil efektivitas temperatur pada alat penukarkalor pada kondisi untai uji tertutup. Hasil penelitian dengan kondisi untai tertutup menunjukkan bahwa padadebit aliran 0,377 L/s di dapat nilai efektifitas sebesar 0,35. Kemudian Pada debit aliran 0,472 L/s di dapat nilaiefektifitas sebesar 0,30 , dan pada debit aliran 0,567 di dapat nilai efektifitas sebesar 0,25. Dan ahasil analisapada eksperimen menunjukan bahwa debit aliran air mempengaruhi terhadap efektivitas pertukaran kalor padaalat penukar kalor dimana semakin besar debit aliran maka semakin kecil nilai efektivitasnya.
REACTOR CAVITY COOLING SYSTEM WITH PASSIVE SAFETY FEATURES ON RDE: THERMAL ANALYSIS DURING ACCIDENT Rahayu Kusumastuti; Sriyono Sriyono; Mulya Juarsa; Hendro Tjahjono; I. D. Irianto; Topan Setiadipura; D. H. Salimy; A. Hafid
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 21, No 2 (2019): JUNI 2019
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1878.724 KB) | DOI: 10.17146/tdm.2019.21.2.5499

Abstract

Reaktor Daya Eksperimental (RDE) is an experimental power reactor based on HTGR technology that implements inherent safety system. Its safety systems are in compliance with “defense in depth” philosophy. RDE is also equipped with reactor cavity cooling system (RCCS) used to remove the heat transferred from the reactor vessel to the containment structure. The RCCS is designed to fulfil this role by maintain the reactor vessel under the maximum allowable temperature during normal operation and protecting the containment structure in the event of failure of all passive cooling systems. The performance and reliability of the RCCS, therefore, are considered as critical factors in determining maximum design power level related to heat removal. RCCS for RDE will use a novel shape to efficiently remove the heat released from the RPV through thermal radiation and natural convection. This paper discusses the calculation of RCCS thermal analysis during accident. The RPV temperature must be maintained below 65ºC. The accident is assumed that there is no electricity from diesel generator supplied to the blower. The methodology used is based on the calculation of mathematical model of the RCCS in the passive mode. The heat is released through cavity by natural convection, in which the RCCS is capable to withdraw the heat at the rate of 50.54 kW per hour.Keywords: Passive safety, RCCS, RDE, Thermal analysis
DEVELOPMENT OF EXPERIMENTAL POWER REACTOR (EPR) MODEL FOR SAFETY ANALYSES USING RELAP5 Andi Sofrany Ekariansyah; Muhammad Subekti; Surip Widodo; Hendro Tjahjono; Susyadi Susyadi; Puradwi Ismu Wahyono; Anwar Budianto
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 21, No 2 (2019): JUNI 2019
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1853.799 KB) | DOI: 10.17146/tdm.2019.21.2.5449

Abstract

Pebble bed reactor design, classified as the high temperature gas-cooled reactor (HTGR), is currently being part of BATAN main program to promote nuclear energy by starting the Experimental Power Reactor (EPR) program since 2015. Starting from 2018, the detail design document has to be submitted into nuclear regulatory body for further assessment. Therefore results of design analysis have to be supplemented by performing a design evaluation, which can be achieved by developing the model of the EPR.  The development is performed using RELAP5/SCDAP/Mod.3.4 as the thermal-hydraulic analysis code validated for the light-water reactor having module for the pebble fuel element and non-condensable helium gas. Methodology of model development consists of defining the helium flow path inside the reactor pressure vessel, modelling of pebble bed core including its power distribution, and modelling of reflector components to be simulated under 100 % core power. The developed EPR model results in design parameters, which confirm the main thermal data of the EPR, including the pebble and reflector temperatures. The peak pebble temperature is calculated to be 1,375 °C, which requires further investigations in the model accuracy, since the reference values are around 1,015 °C, even it is below the pebble temperature limit. For safety analysis, the EPR model can be used under nominal core flow condition, which produces more conservative results by paying attention on the RELAP5 specific modules for the pebble bed-gas cooled system.Keywords: experimental power reactor, development, RELAP5, steady-state
PRELIMINARY ASSESSMENT OF ENGINEERED SAFETY FEATURES AGAINST STATION BLACKOUT IN SELECTED PWR MODELS Andi Sofrany Ekariansyah; Surip Widodo; Susyadi Susyadi; Hendro Tjahjono
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 23, No 2 (2021): June 2021
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/tdm.2021.23.2.6204

Abstract

The 2011 Fukushima accident did not prevent countries to construct new nuclear power plants (NPPs) as part of the electricity generation system. Based on the IAEA database, there are a total of 44 units of PWR type NPPs whose constructions are started after 2011. To assess the technology of engineered safety features (ESFs) of the newly constructed PWRs, a study has been conducted as described in this paper, especially in facing the station blackout (SBO) event. It is expected from this study that there are a number of PWR models that can be considered to be constructed in Indonesia from the year of 2020. The scope of the study is PWRs with a limited capacity from 900 to 1100 MWe constructed and operated after 2011 and small-modular type of reactors (SMRs) with the status of at least under licensing. Based on the ESFs design assessment, the passive core decay heat removal has been applied in the most PWR models, which is typically using steam condensing inside heat exchanger within a water tank or by air cooling. From the selected PWR models, the CPR-1000, HPR-1000, AP-1000, and VVER-1000, 1200, 1300 series have the capability to remove the core decay heat passively. The most innovative passive RHR of AP-1000 and the longest passive RHR time period using air cooling in several VVER models are preferred. From the selected SMR designs, the NuScale design and RITM-200 possess more advantages compared to the ACP-100, CAREM-25, and SMART. NuScale represents the model with full-power natural circulation and RITM-200 with forced circulation. NuScale has the longest time period for passive RHR as claimed by the vendor, however the design is still under licensing process. The RITM-200 reactor has a combination of passive air and water-cooling of the heat exchanger and is already under construction.  
IbM KELOMPOK USAHA CAMILAN “SUMBER REJEKI” Suparno Suparno; Dantje Salean; Hendro Tjahjono
JPM17: Jurnal Pengabdian Masyarakat Vol 1 No 02 (2015)
Publisher : Lembaga Penelitian dan Pengabdian kepada Masyarakat

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.30996/jpm17.v1i02.542

Abstract

“Sumber Rejeki” micro owner is Mr.Suwito and Mr. Adi Suprianto which located at Desa Cangkring Kecamatan Ngadirojo Kabupaten Pacitan. This business has been established in 2007 and operated in the field of business Kolong Klitik. The main problems faced through “Sumber Rejeki” micro business are the quantity of production is not optimal yet and both could’nt make financial bookkeeping business and less distribution. By using science and technology from the Ipteks bagi Masyarakat (IbM) can be expected improving the quantity and quality of Kolong Klitik production, as well as to make financial efforts and to expand marketing network.Keywords : Production, Finance and Marketing.
Analisis Pengaruh Kepemimpinan dan Komunikasi Terhadap Motivasi dan Kinerja Pegawai (Satuan Polisi Pamong Praja Kota Surabaya) Muhammad Rodhiyallah; Amiartuti Kusmaningtyas; Hendro Tjahjono
Jurnal Bisnis dan Keuangan Vol 2 No 1 (2017): Business and Finance Journal
Publisher : UNUSA Press

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.33086/bfj.v2i1.467

Abstract

The aim of the study was to analyze and determine the influence of leadership and communication, on employee motivation and performance at Satuan Polisi Pamong Praja Kota Surabaya. Branch, as many as 100 persons. Sampling technique samples (Slovin) data was analyzed with multiple linear regression with SPSS for windows program. The result of the research indicated that leadership, communication, and motivation simultaneously have significant effect on employees’ performances with determination value of 0,424 or 4,24%. Leadership, communication and motivation partially has significant effect on performance. Communication itself has dominant effect on employee’s performance.
THE PRELIMINARY STUDY ON IMPLEMENTING A SIMPLIFIED SOURCE TERMS ESTIMATION PROGRAM FOR EARLY RADIOLOGICAL CONSEQUENCES ANALYSIS Theo Alvin Ryanto; Jupiter Sitorus Pane; Muhammad Budi Setiawan; Ihda Husnayani; Anik Purwaningsih; Hendro Tjahjono
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 25, No 2 (2023): June 2023
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2023.6869

Abstract

Indonesia possesses numerous potential sites for nuclear power plant development. A fast and comprehensive radiological consequences analysis is required to conduct a preliminary analysis of radionuclide release into the atmosphere, including source terms estimation. One simplified method for such estimation is the use of the Relative Volatility approach by Kess and Booth, published in IAEA TECDOC 1127. The objective of this study was to evaluate the use of a simple and comprehensive tool for estimating the source terms of planned nuclear power plants to facilitate the analysis of radiological consequences during site evaluation. Input parameters for the estimation include fuel burn-up, blow-down time, specific heat transfer of fuel to cladding, and coolant debit, using 100 MWe PWR as a case study. The results indicate a slight difference in the calculated release fraction compared to previous calculations, indicating a need to modify Keywords: Source terms, Relative volatility, Release fraction, PWR, SMART
Co-Authors A. Hafid Amiartuti Kusmaningtyas Andi Sofrany Ekariansyah Andi Sofrany Ekariansyah Andi Sofrany Ekariansyah Anik Purwaningsih Anwar Budianto D. H. Salimy Dantje Salean Gregorius Bambang Heru I. D. Irianto Ihda Husnayani Jupiter Sitorus Pane Muhammad Budi Setiawan Muhammad Hadi Kusuma Muhammad Rodhiyallah Muhammad Subekti Mulya Juarsa Puradwi Ismu Wahyono Rahayu Kusumastuti Sriyono Sriyono Suhendra Suhendra Suparno Suparno Surip Widodo Susyadi Susyadi Theo Alvin Ryanto Topan Setiadipura Yogi Sirodz Gaos