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All Journal SIGMA EPSILON - Majalah Ilmiah Teknologi Keselamatan Nuklir Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Ganendra: Majalah IPTEK Nuklir Jurnal Pengembangan Energi Nuklir

Geni Rina Sunaryo

Unknown Affiliation

Author-ID : 2788957

Computer Science & IT Decision Sciences, Operations Research & Management Earth & Planetary Sciences Electrical & Electronics Engineering Energy Engineering Environmental Science Industrial & Manufacturing Engineering Materials Science & Nanotechnology Social Sciences Other

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Articles

KARAKTERISASI MIKROBA DALAM AIR PENDINGIN SEKUNDER RSG-GAS Itjeu Karliana; Geni Rina Sunaryo; Diah Erlina
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 12, No 3 (2008): Agustus 2008
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/sigma.2008.12.3.2933

Telah diperoleh hasil identifikasi karakteristik bakteri yang terkandung dalam air sistem pendingin sekunder RSG-GAS berdasarkan sifat-sifat morfologi sel, sifat-sifat fisiologi sel dan respon terhadap reaksi karbohidrat serta dihitung jumlah koloni bakteri dengan metode total plate count. Sampling air dilakukan pada beberapa tempat antara lain di kolam pendingin sekunder (1), setelah lewat kran (2), seteleh sistem penukar panas (3), dan air masuk ke kolam pendingin setelah lewat kran (4). Sampel dianalisis secara mikrobiologi menurut prosedur Bergey’s Manual. Berdasarkan hasil isolasi, telah teridentifikasi adanya spesies bakteri pereduksi sulfat dari species desulfococcus multivoran. Masing-masing, lokasi (1) mengandung 7,4 x 104 cfu/ml, lokasi (2) 6,9 x 104 cfu/ml, lokasi (3) 2,8 x 104 cfu/ml, dan lokasi (4) 1,9 x 104 cfu/ml. Hasil analisis dari keempat lokasi diperoleh bahwa kandungan bakteri masih dibawah spesifikasi air pendingin sekunder yaitu <106 cfu/ml. Ukuran mikro partikel bakteri 0,5 μ masih mampu lolos dari sistem filtrasi air pendingin kecuali memakai filter bakteri semi permeable berukuran 0,22 μ. Keberadaan bakteri pereduksi sulfat yang terakumulasi membentuk lapisan dapat menimbulkan biokorosi dan pada suatu saat dapat menurunkan kemampuan sistem pertukaran panas.

PERFORMANCE ANALYSIS OF HELIUM INVENTORY CONTROL OF RGTT200K COOLING SYSTEM Sriyono Sriyono; Rahayu Kusumastuti; Sofia Butarbutar; Geni Rina Sunaryo
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 19, No 1 (2015): Februari 2015
Publisher : Badan Tenaga Nuklir Nasional

RGTT200K is a power reactor, designed based on HTGR tech-nology having capability to operate at high temperatures. RGTT200K features are 200 MWth power, helium-cooled, graphite moderator and reflector, pebble fuel type, and uses the Brayton direct cycle. Helium Inventory Control System (HICS) is one of its safety system which maintains the pressure, the helium coolant quality and quantity to meet safety requirements. The HICS consists of 3 subsys-tems, namely: Inventory Control System (ICS), Helium Purification System (HPS), and Helium Make-Up System (HMS). All of the systems have the function to maintain pressure, helium quality and quantity so that the reactor can operate reliable and safely. This paper discusses the performance of the ICS, which is integrated to the reactor coolant. The research objective was to determine the helium storage tank response rate, when primary coolant is overpressured and depressurized. The methodology used in this research is modeling and simulation by using ChemCAD. In previous re-search, the HPS, ICS and HMS have been modeled but have not been integrated yet in to the primary coolant. The simulation results showed that the time required for the injection tank back to the cool-ant normal pressure of 52 bars, due to depressurization up to 5 % was 160 seconds. While the time required for bleeding / blowdown to the storage tanks due to overpressurization up to 5 % was 186 seconds.

Studi Radiolisis Air Ringan dan Pengukuran Laju Dosis Bahan Bakar Terhadap Jarak Sumber Radiasi Pada Kolam Penyimpanan Bahan Bakar Bekas (ISSF) Cyntia Agustin; M Romli; Sofia Loren Butar-butar; Rahayu Kusumastuti; Sriyono Sriyono; Geni Rina Sunaryo
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 22, No 2 (2018): November 2018
Publisher : Badan Tenaga Nuklir Nasional

Studi Literatur Radiolisis Air Ringan dan Pengukuran Laju Dosis Bahan Bakar Terhadap Jarak Sumber Radiasi Pada Kolam Penyimpanan Bahan Bakar Bekas (ISSF). . Elemen bahan bakar bekas masih mengandung sejumlah uranium diperkaya dengan paparan radiasi yang sangat tinggi, sehingga digunakan air sebagai media penyimpanan bahan bakar bekas pada kolam ISSF agar paparan radiasi bahan bakar tidak keluar ke lingkungan.Paparan radiasi dalam air dapat menyebabkan adanya pembentukan oksidator yang dapat menyebabkan korosi pada material bahan ISSF. Laju dosis dapat terukur dalam suatu sumber radiasi terhadap besarnya penahan radiasi. Laju dosis ini digunakkan sebagai input parameter untuk reaksi radiolysis sehingga konsentrasi pembentukan oksidator dalam air dapat diprediksi. Hubungan antara laju dosis teradap jarak sumber radiasi (tebal penahan) menjadi penting untuk penerapan proteksi radiasi. Metode untuk mengukur laju dosis pada kolam ISSF dilakukan pada rak bahan bakar bekas serta uji cicip pada sebuah kelongsong bahan bakar bekas. Laju dosis diukur dengan detector radiagem dengan kabel yang terbungkus plastik. Data hasil percobaan didapatkan bahwa hubungan antara laju dosis radiasi terhadap sumber radiasi yaitu semakin besar jarak detektor terhadap sumber radiasi semakin kecil laju dosis yang terukur dan bersifat eksponensial.Kata Kunci : Kolam ISSF, radiasi, radiolysis air, laju dosis, detector

PREDICTION OF REMAINING USEFUL LIFE FOR COMPONENTS IN SSC OF RSG-GAS BASED ON RELIABILITY ANALYSIS Entin Hartini; Endiah Puji Hastuti; Geni Rina Sunaryo; Aep Saepudin; Sri Sudadiyo; Amir Hamzah; Mike Susmikanti
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 24, No 1 (2022): February (2022)
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/tdm.2022.24.1.6400

In the maintenance system, efforts are needed to improve the effectiveness of the maintenance system and organization. For effective maintenance planning it is necessary to have a good understanding of the reliability and component availability of the system. For this reason, it is necessary to determine the remaining component life using Remaining Useful Life (RUL), so that maintenance tasks can be planned effectively. The purpose of this study is to determine the remaining life of the safety A component from SSC RSG-GAS based on reliability analysis. The method used in this paper is a statistical approach to estimating RUL. The Weibull hazard model is determined for modeling the hazard function so that it can be integrated in the reliability analysis. The model is verified using data from the safety A component from the SSC RSG-GAS. The results obtained from the analysis are useful for estimating the remaining useful lives of these components which can then be used to plan for effective maintenance and help control unplanned outages. The results obtained can be used for maintenance development and preventive repair planning.

THERMODYNAMICS ANALYSES ON REGENERATIVE STEAM CYCLE WITH TWO TANKS FOR HTGR-10 CONCEPT Sri Sudadiyo; Geni Rina Sunaryo
GANENDRA Majalah IPTEK Nuklir Volume 20 Nomor 2 Juli 2017
Publisher : Website

In this work, steam cycle from a nuclear power plant is explored in order to increase efficiency and electric power output. A thermal source in the form of a HTGR-10 concept is considered. The power conversion unit of HTGR-10 consists of steam generator, turbine, condenser, pump, and connecting pipes. Helium is used as the core coolant and the working fluid for power conversion unit is water/steam. The proposed thermodynamic process modification has been evaluated for regenerative steam power cycle of this reactor. The scope of study covered regenerative steam cycle with two tanks including feed water tank and intermediate feed water tank. The evaluation analyzes the effect of pressure, efficiencies of turbine and pumps, and tanks against thermal efficiency. The Cycle-Tempo software is used to simulate and optimized this effect on steam cycle based on HTGR-10. The results indicate improvements of as much as 2.65 % in thermal efficiency and 0.271 MWe in electric power.

ANALYSIS ON AlMg2 AS RSG-GAS CLADDING MATERIAL CORROSION IN CHLORIDE CONTAINING WATER Febrianto Bahar; Sriyono Sriyono; Geni Rina Sunaryo
GANENDRA Majalah IPTEK Nuklir Volume 21 Nomor 2 Juli 2018
Publisher : Website

AnalYsis On AlMg2 AS RSG-GAS CLADDING material corrosion IN CHLORIDE CONTAINING WATER. The AlMg2is one of an alluminium alloy that used as cladding material for the RSG GA. Siwabessy (RSG-GAS) research reactor in Serpong, Indonesia. The reactor uses demineralized water as primary coolant with 6.5 to 7.5 of pH. A poor treatment of water in primary coolant can lead to the problem of AlMg2 integrity. The primary coolant concentration of chloride must lower than 0.0094 ppm to protect cladding corrosion. The purpose of this study is to determine the effect of temperature and chloride ion concentration to AlMg2. The method in this research is to observe the corrosion rate for AlMg2 material by using Potentiostat. The laboratory experiments were conducted in various temperatures (28, 35, 40 and 45°C) and concentration of sodium chloride of 0.005, 0.010, 0.015, 0.020, 0.025, 0.030 and 0.035 ppm. The results show the corrosion rates were very small, and the highest corrosion rate occurred is 1.23 x 10-3mpy in 0.035 ppm of NaCl at 45°C .

APLIKASI MSC PATRAN UNTUK PENENTUAN RENTANG MAKSIMUM PENYANGGA PIPA PRIMER REAKTOR AP1000 Elfrida Saragi; Abdul Hafid; Geni Rina Sunaryo
Jurnal Pengembangan Energi Nuklir Vol 17, No 1 (2015): Juni 2015
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2015.17.1.2613

ABSTRAK APLIKASI MSC PATRAN UNTUK PENENTUAN RENTANG MAKSIMUM PENYANGGA PIPA PRIMER REAKTOR AP1000. Penyangga pipa digunakan antara lain untuk menjaga agar pipa tidak membebani komponen dan mencegah terjadinya lendutan yang berlebihan. Penentuan posisi penyangga pipa ditetapkan oleh beberapa faktor, seperti adanya katup, adanya belokan pipa dan jarak antara dua komponen utama reaktor yaitu tangki reaktor dan pembangkit uap.Untuk transpor panas dari tangki reaktor ke pembangkit uap digunakan pipa hotleg. Tujuan penelitian ini adalah untuk dapat menentukan batas jarak penyangga yang baik dan sudut belok pipa pada pipa primer reaktor daya AP1000 berdiameter 37,5inchi diameter luar dan 31 inchi diameter dalam. Metode analisis yang digunakan adalah metode komputasi dengan pemodelan menggunakan software MSC Patran.Hasil perhitungan menunjukkan bahwa semakin jauh jarak penyangga pipa maka besar lendutan yang terjadi makin besar.Nilai maksimal yang cukup baik dan sesuai standar ASME adalah pada jarak 5 m dengan sudut belok pipa 45 derajat.Pada jarak tersebut defleksi maksimumyang terjadi sebesar 1.76 cm dan tegangan tekuk sebesar 2.06 MPa. Kata kunci: Tegangan tekuk, Defleksi, Penyangga pipa, Hotlegreaktor AP1000. ABSTRACT APPLICATION OF MSC-PATRANTO DETERMINE THE MAXIMUM RANGE SUPPORT OF PRIMARY PIPES NUCLEAR REACTOR AP1000. Pipe supports used among others, to keep the pipes from overloding the components and prevent excessive deflection. The position of the pipe support is determined by several factors, such as the presence of valves, pipe bends and the distance between the two main components of reactor. Heat transport from reactor tank to the steam generatorare performed using hotleg pipe. The purpose of this study was to determine a safe support distance limit and the angle of the pipe turn and bendingon the primary pipe of AP1000 power reactor with the outer pipe diameter of 37.5 inches, and the inner diameter of the pipe is 31 inches.The analytical method used is the computational modeling methodsusing the MSC Patran software. The calculation resultsshow that the greater the distance of the pipe support, then deflection occurs is greater. The maximum value that is quite good, andin accord to ASME standards is at a distance of 5 meter and the angle of pipe turn is 45 degree. At that distance, the maximum deflection occurs is 1.76 cm and bending stress is 2.06 MPa. Keywords: Deflection, Bending stress, Support pipes, Hotleg reactor AP1000.

Temperature Dependence of Primary Species G(values) Formed from Radiolysis of Water by Interaction of Tritium β-Particles Sofia Loren Butarbutar; Sriyono Sriyono; Geni Rina Sunaryo
Jurnal Pengembangan Energi Nuklir Vol 19, No 1 (2017): Juni 2017
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2017.19.1.3134

TEMPERATURE DEPENDENCE OF PRIMARY SPECIES G(VALUES) FORMED FROM RADIOLYSIS OF WATER BY INTERACTION OF TRITIUM β-PARTICLES. G(values) are important to understand the effect of radiolysis of Nuclear Power Plant (NPP) cooling water. Since direct measurements are difficult, hence modeling and computer simulation were carried out to predict radiation chemistry in and around reactor core. G(values) are required to calculate the radiation chemistry. Monte Carlo simulations were used to calculate the G(values) of primary species , H•, H2, •OH dan H2O2 formed from the radiolysis of tritium β low energy electron. These radiolytic products can degrade the reactor components and cause corrosion under the reactor operating conditions. G(values) prediction can indirectly contribute to maintain the material reliability. G(values) were calculated at 10-8, 10-7, 10-6 and 10-5 s after ionization at temperature ranges. The calculation were compared with the G(values) of g-ray 60Co. The work aimed to understand temperature effect on the water radiolysis mechanism by the tritium β electron. The results show that the trend similarity was found on the temperature dependence of G(values) of tritium β electron and g-ray 60Co. For tritium β electron, G(values) for free radical were lower than g-ray 60Co, but higher for molecular products as temperature raise at 10-8 and 10-7. The significant differences for these two type of radiations were on G(H2), G(•OH) and G(H•) at 10-6and 10-5 s above 200 oC.

Co-Authors Abdul Hafid Aep Saepudin Cyntia Agustin Diah Erlina Elfrida Saragi Endiah Puji Hastuti Entin Hartini Febrianto Bahar I Gusti Bagus Wiksuana Itjeu Karliana M Romli Mike Susmikanti Rahayu Kusumastuti Rahayu Kusumastuti Sofia Butarbutar Sofia Loren Butar-butar Sofia Loren Butarbutar Sri Sudadiyo Sri Sudadiyo Sriyono Sriyono

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