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INDONESIA
Jurnal Pengembangan Energi Nuklir
Published by Badan Tenaga Nuklir Nasional
ISSN : 14109816     EISSN : 25029479     DOI : https://doi.org/10.17146/jpen
Core Subject : Science, Social, Engineering,
Decision Sciences, Operations Research & Management Earth & Planetary Sciences Electrical & Electronics Engineering Energy Engineering Environmental Science Industrial & Manufacturing Engineering Social Sciences
Jurnal Pengembangan Energi Nuklir publishes scientific papers on the results of studies and research on nuclear energy development with the scope of energy and electricity planning, nuclear energy technology, energy economics, management of nuclear power plants, national industries that support nuclear power plants, aspects of the nuclear power plant site and environment, and topics others that support the development of nuclear energy.
Arjuna Subject : Energi (semua kategori) - Teknik dan Energi Nuklir
Articles 9 Documents
 1 
Search results for , issue "Vol 20, No 1 (2018): Juni 2018" : 9 Documents clear
Reviu Implementasi Thorcon Molten Salt Reactor di Indonesia Sahala Maruli Lumbanraja; Edwaren Liun
Jurnal Pengembangan Energi Nuklir Vol 20, No 1 (2018): Juni 2018
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2018.20.1.4083

Abstract

REVIU IMPLEMENTASI THORCON MOLTEN SALT REACTOR DI INDONESIA.  Thorcon Molten Salt Reactor (Thorcon MSR) merupakan jenis PLTN generasi ke-4 yang dirancang oleh Martingle Inc. Amerika Serikat. PLTN ini berbahan bakar, dan berpendingin garam cair , beroperasi pada temperatur tinggi dan tekanannya mendekati tekanan atmosfir. PLTN ini berdaya 1000 MWe yang dihasilkan oleh 4 modul dengan daya masing-masing 250 MWe. Makalah ini bertujuan untuk menguraikan dan memberi gambaran tentang kelayakan ThorCon MSR kepada pemangku kepentingan ketika akan diimplementasikan di Indonesia. Metodologi yang digunakan adalah mempelajari berbagai pustaka tentang teknologi Thorcon, ketersediaan  SDM, partisipasi nasional dan regulasinya, serta dilakukan dengan analisis SWOT (Strength, Weaknesses, Opportunities, Threats). Jenis PLTN ini layak diimplementasikan dalam jangka panjang di Indonesia karena mempunyai aspek keselamatan tinggi, dan mudah dikonstruksi tetapi berbagai kendala masih perlu diselesaikan seperti status teknologi masih desain konsep, SDM belum tersedia, dan belum mendapat sertifikasi dari lembaga yang berwenang.
Hal Muka JPEN 2018 Volume 20 Nomor 1 Juni JPEN JPEN
Jurnal Pengembangan Energi Nuklir Vol 20, No 1 (2018): Juni 2018
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2018.20.1.4522

Abstract

Penelitian dan Pengembangan Material Struktur Reaktor Maju Ferhat Aziz
Jurnal Pengembangan Energi Nuklir Vol 20, No 1 (2018): Juni 2018
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2018.20.1.4143

Abstract

PENELITIAN DAN PENGEMBANGAN MATERIAL STRUKTUR REAKTOR MAJU. Pengoperasian suatu pembangkit listrik tenaga nuklir secara selamat dan ekonomis sangat tergantung kepada ketersediaan material struktur yang handal. Selama umur operasi reaktor yang dewasa ini mencapai 60 tahun, material struktur terpapar temperatur yang tinggi, lingkungan korosif dan medan radiasi kuat yang terjadi akibat proses fisi. Struktur penopang bahan bakar akan memiliki umur lebih singkat dalam lingkungan demikian. Sementara itu tuntutan dalam pengembangan reaktor maju masa depan adalah temperatur operasi dan burnup yang lebih tinggi untuk meningkatkan efisiensi operasi reaktor. Material yang mampu mengatasi kondisi itu harus stabil secara dimensional dalam medan radiasi, baik dengan maupun tanpa adanya stress, serta memiliki sifat yang baik di lingkungan yang korosif. Makalah ini menelaah secara singkat litbang material struktur reaktor yang potensial digunakan dalam sistem reaktor maju, seperti baja  ferritic/martensitic, baja ODS, dan keramik, termasuk sintesis baja ODS yang dikembangkan di BATAN. Selain itu dikaji pula kerusakan radiasi pada material struktur serta sintesis dan simulasi kinerja perisai radiasi menggunakan paket program MCNP5. Hasil kajian menunjukkan bahwa walaupun hasil yang ada sudah cukup baik, masih diperlukan litbang lebih lanjut guna mendapatkan material yang memenuhi kriteria yang diinginkan, baik melalui eksperimen maupun secara simulasi dan pemodelan dengan komputer.
Hal Belakang JPEN 2018 Volume 20 Nomor 1 Juni JPEN JPEN
Jurnal Pengembangan Energi Nuklir Vol 20, No 1 (2018): Juni 2018
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2018.20.1.4523

Abstract

Component Analysis of Purification System of RSG-GAS Mike Susmikanti; Entin Hartini; Aep Saepudin; Jos Budi Sulistyo
Jurnal Pengembangan Energi Nuklir Vol 20, No 1 (2018): Juni 2018
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2018.20.1.4095

Abstract

COMPONENT ANALYSIS OF PURIFICATION SYSTEM OF RSG-GAS. Component reliability analysis is required in the aging management of RSG-GAS that has reached an age of 30 years. One of the required analyses is the assessment of the distribution of repair data and the estimation of related parameters. The Primary Purification System (KBE01) and the Purification and Warm Water Layer System (KBE02) are important components of RSG-GAS. By knowing the repair data distribution, the parameters of the most frequently occurring component repair and the average of the repair period can be estimated, so that the required provision of spare parts for the smooth operation of the reactor can be predicted. The purpose of this study is to analyze the components of the KBE01 and KBE02 systems through the data distribution approach using the matching test method. With the matching test, the form of data distribution can be determined, so the parameter of the average component repair period that can be used as a comparison of the maintenance period of the components can be estimated. The repair times of KBE01 and KBE02 in RSG-GAS on Core 52 through Core 88 (2006-2015) were analyzed using goodness-of-fit test. The repair times of AA068 and AP001 KBE01 follow the exponential distribution with average repair times of 631.6 and 451.2 days, respectively. The repair times of WWL and AA002 KBE02 followed an exponential distribution with average repair times of 239.5 days and 888.0 days.
Penentuan Nilai Jarak Aman Sumber Tidak Bergerak: Skenario Kebakaran dan Ledakan pada SPBU dan SPPBE di Sekitar Tapak RDE Dedy Priambodo
Jurnal Pengembangan Energi Nuklir Vol 20, No 1 (2018): Juni 2018
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2018.20.1.4314

Abstract

PENENTUAN NILAI JARAK AMAN SUMBER TIDAK BERGERAK: SKENARIO KEBAKARAN DAN LEDAKAN PADA SPBU DAN SPPBE DI SEKITAR TAPAK RDE. Nilai jarak aman (Screening Distance Value, SDV) untuk tiap-tiap jenis sumber bahaya harus ditentukan menggunakan pendekatan konservatif sehingga pengaruh kejadian interaksi yang berada di luar jarak ini tidak perlu diperhitungkan lebih lanjut. Dari pengamatan, sumber tidak bergerak yang paling banyak berada di sekitar tapak adalah Stasiun Pengisian Bahan Bakar Umum (SPBU) dan Stasiun Pengangkutan dan Pengisian Bulk Elpiji (SPPBE). Oleh karena itu, penelitian ini bertujuan untuk menentukan SDV dari SPBU dan SPPBE untuk skenario ledakan dan kebakaran dengan lokasi studi di sekitar tapak Reaktor Daya Eksperimental (RDE), Puspiptek Serpong. Studi ini menggunkan Areal Location Of Hazardous Atmospheres (ALOHA) untuk mensimulasikan zona ancaman ledakan dan kebakaran dari substansi Bensin dan LPG. Simulasi ini melibatkan ledakan dan kebakaran iso-oktana di  SPBU dan butane di SPPBE untuk menganalisis zona ancaman dari skenario kecelakaan. Diketahui bahwa SDV sangat tergantung dari jenis, maupun kapasitas material berbahaya, skenario kecelakaan serta kondisi atmosfer pada sumber bahaya tersebut. Dari penelitian ini, diketahui pula suatu sumber bahaya bisa mempunyai SDV lebih dari satu nilai. SDV SPBU berkapasitas 170.000 liter untuk skenario kebakaran 976 m dan 1.200 m, sedangkan untuk skenario ledakan adalah 958 m dan 1.200 m. SDV SPPBE berkapasitas 25.000 kg untuk skenario kebakaran 445 m dan 565 m, sedangkan untuk skenario ledakan adalah 430 m dan 573 m. Sementara SDV SPPBE berkapasitas 100.000 kg untuk skenario kebakaran 913 m dan 1.100 m, sedangkan untuk skenario ledakan adalah 758 m dan 1.100 m. Studi ini dapat memberikan alternatif penentuan nilai SDV pada studi dan evaluasi tapak reaktor nuklir.
Study of Dispersion Hazard Potential of The LPG Stations Around the RDE Site in Rainy and Dry Season Siti Alimah; June Mellawati
Jurnal Pengembangan Energi Nuklir Vol 20, No 1 (2018): Juni 2018
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2018.20.1.4305

Abstract

STUDY OF DISPERSION HAZARD POTENTIAL OF THE LPG STATIONS AROUND THE RDE SITE IN RAINY AND DRY SEASON. There are two LPG station (SPPBE) which are the depot of filling, storage and distribution of  Liquid Petroleum Gas (LPG) namely PT. BM and PT. ISR which the distance each are 2,995 and 4,141 km from Experimental Power Reactor (RDE) site with capacity 15 and 30 tons. LPG station is a stationary source, which is one aspect of the external human induced events that need to be analyzed in the preparation of site evaluation reports to obtain site permits. Hazard potential that may occur from the depot LPG are fire, explosion and dispersion of hazardous and toxic gas. The release of LPG due to valve leakage which is then dispersed at a certain dose has potentially harmful to health, even death to the population around  the RDE site. The purpose of the study was to know the effect of seasons (rainy and dry) to the potential hazard of LPG dispersion from LPG truck tank valve to the around RDE site. The method of study are collection the atmospheric data such as wind direction and speed, temperature and humidity, collection the station LPG characteristic, such as mass of gas, diameter and length of tank, and valve diameter, etc. The atmospheric data was obtained from Pondok Betung Climatology Station, in dry, transition, and rainy seasons, furthermore data was analyzed using ALOHA software version 5.4.5. The results show dispersion from LPG release due to valve  leakage from PT. BM and PT. ISR around the RDE site, in the dry season (April), the transition (January and July) as well as the rainy season (October) does not hazardous to the RDE site. Maximum threat zone occurs in dry season at April (wind speed 1.54 m/s), which reaches radius 179 m with airborne LPG concentration 5500 ppm, radius 111 m with concentration 17000 ppm and radius 71 m with concentration 53000 ppm.
Conceptual Design On N16 Decay Chamber For Modified TRIGA-2000 With Plate-Type Fuel Sukmanto Dibyo; Surian Pinem; V.I.S Wardhani
Jurnal Pengembangan Energi Nuklir Vol 20, No 1 (2018): Juni 2018
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2018.20.1.4278

Abstract

Conceptual Design On N16 Decay Chamber For Modified TRIGA-2000 With Plate-Type Fuel. the TRIGA-2000 is a research reactor in bandung that will be modified using plate-type fuel. The reactor core cooling system is changed from the natural convection cooling mode to the forced convection mode. The purpose of the study is to assess the conceptual design for the decay chamber of N16 nuclide in the primary cooling system of the reactor. In this design, the hold-up system decays the nuclide of N16 resulted from neutron activation product. In the period of 50 seconds, the activity of N16 (T1/2= 7.13 seconds) decays 7 time from half life to low level. The cube shape of decay chamber is provided a plate with 4 hollows and facility to flush the cavitation bubbles. The decay chamber, which is submerged into the bulk shielding as located outside of the reactor pool. The conceptual design uses the Fluent software compared with the analytical estimation for flow velocity in the decay chamber. The result shows a good agreement range with the analytical estimations. The uniform flow profile can be obtained at the velocity of about 0.4 m/s. Water flow life time of 50 seconds in the decay chamber with the capacity of 3.5 m3 is able to decay the N16 nuclide to low level. This decay chamber is expected to contribute in completing the design of reactor primary coolant system using the forced convection mode.
The Implementation of Importance Measure Approaches for Criticality Analysis in Fault Tree Analysis: A Review Julwan Hendry Purba; Deswandri Deswandri
Jurnal Pengembangan Energi Nuklir Vol 20, No 1 (2018): Juni 2018
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2018.20.1.4257

Abstract

THE IMPLEMENTATION OF IMPORTANCE MEASURE APPROACHES FOR CRITICALITY ANALYSIS IN FAULT TREE ANALYSIS: A REVIEW.Fault tree analysis (FTA) has been widely applied in nuclear power plant (NPP) probabilistic safety assessment to evaluate the reliability of a safety system. In FTA, criticality analysis is performed to identify the weakest paths in the system designs and components. For this purpose, an importance measure approach can be applied. Risk managers can apply information obtained from this analysis to improve safety by implementing risk reduction measure into the new design or build a more innovative design. Various importance measure approaches have been developed and proposed for criticality analysis in FTA. Each important measure approach offers specific purposes and advantages but has limitations. Therefore, it is necessary to understand characteristics of each approach in order to select the most appropriate approach to reach the purpose of the study. The objective of this study is to review the current implementations of importance measure approaches to rank individual basic events and/or minimal cut sets regarding their contributions to the unreliability or unavailability of NPP safety systems. This study classified importance measure approaches into two groups, i.e. probability–based importance measure approaches and fuzzy–based importance measure approaches. This study concluded that clear understanding of the purpose of the study, the type of reliability data at hands, and the uncertainty in the calculation need to be considered prior to the selection of the appropriate importance measure approach to the study of interest. 

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