Cooling passive safety features of Reaktor Daya Eksperimental

Setiadipura, Topan; Bakhri, Syaiful; Sunaryo, Geni Rina; Wisnusubroto, Djarot S.

doi:10.1063/1.5046618

Cited by 22 publications

(11 citation statements)

References 9 publications

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“…On the Figure 3, the pebble temperature distribution is showed axially from the top of the core (1 st segment) to the bottom of the core (10 th segment) in the middle core zone or in the 9 th segment for the other 3 core zones. The pebble temperature should not exceed the limit temperature in the SiC layer of 1620 °C [4,13,14]. From the 4 core zones, 3 zones (P-117 to P-119) show the pebble temperatures below the limit value and the middle core zone (P-116) indicates an anomaly in the temperature distribution exceeding the limit.…”

Section: Temperature Distribution For the 4 Core Zonesmentioning

confidence: 99%

“…The PBR also drew attention in Indonesia to be part of the one of national program to support the National Medium Term Development Plant in year 2015 -2019 by starting the Reaktor Daya Eksperimental (RDE) or Experimental Power Reactor (EPR) program in 2015, conducted by the Indonesia National Nuclear Energy Agency (BATAN). The main goal of EPR program is to develop national capability of BATAN in the nuclear reactor technology by mastering the design, construction project management, commissioning and operation of a experimental power reactor [4]. The EPR program was inspired by the China R&D program for the HTGR began in the mid-1970s, which accomplished the construction of the HTR-10 test reactor in the 1990s [5].…”

Section: Introductionmentioning

confidence: 99%

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Preliminary Analysis of Core Temperature Distribution of Experimental Power Reactor Using Relap5

et al. 2018

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High Temperature Gas Cooled Reactor (HTGR) is a high temperature reactor type having nuclear fuels formed by small particles containing uranium in the core. One of HTGR designs is Pebble Bed Reactor (PBR), which utilizes helium gas flowing between pebble fuels in the core. The PBR is also the similar reactor being developed by Indonesia National Nuclear Energy Agency (BATAN) under the name of the Reaktor Daya Eksperimental (RDE) or Experimental Power Reactor (EPR) started in 2015. One important step of the EPR program is the completion of the detail design document of EPR, which should be submitted to the regulatory body at the end of 2018. The purpose of this research is to present preliminary results in the core temperature distribution in the EPR using the RELAP5/SCDAP/Mod3.4 to be complemented in the detail design document. Methodology of the calculation is by modelling the core section of the EPR design according to the determined procedures. The EPR core section consisting of the pebble bed, outlet channels, and hot gas plenum have been modelled to be simulated with 10 MWt. It shows that the core temperature distribution under assumed model of 4 core zones is below the limiting pebble temperature of 1,620 °C with the highest pebble temperature of 1,477.0 °C. The results are still preliminary and requires further researches by considering other factors such as more representative radial and axial power distribution, decrease of core mass flow, and heat loss to the reactor pressure vessel.Keywords: Pebble bed, core temperature, EPR, RELAP5 ANALISIS AWAL DISTRIBUSI TEMPERATUR TERAS REAKTOR DAYA EKSPERIMENTAL MENGGUNAKAN RELAP5. High Temperature Gas Cooled Reactor (HTGR) adalah reaktor tipe temperatur tinggi yang memiliki bahan bakar nukir dalam bentuk bola-bola kecil yang mengandung uranium. Salah satu desain HTGR adalah reaktor pebble bed (Pebble bed reactor/PBR) yang memanfaatkan gas helium sebagai pendingin yang mengalir di celah-celah bahan bakar bola di dalam teras. PBR juga merupakan tipe reaktor yang sedang dikembangkan oleh BATAN dengan nama reaktor daya eksperimental (RDE) yang dimulai pada 2015. Salah satu tahapan penting dalam program RDE adalah penyelesaian dokumen desain rinci yang harus dikirimkan ke badan pengawas pada akhir 2018. Tujuan penelitian adalah untuk menyajikan hasil-hasil awal pada distribusi temperatur di teras RDE menggunakan RELAP5/SCDAP/Mod3.4 sehingga dapat melengkapi isi dokumen desain rinci. Metode perhitungan adalah dengan memodelkan bagian teras RDE sesuai hasil penelitian sebelumnya. Bagian teras RDE yang dimodelkan terdiri dari pebble bed, kanal luaran, dan plenum gas bawah yang disimulasikan pada daya 10 MWt. Hasil simulasi menunjukkan bahwa distribusi temperatur teras dengan asumsi pembagian 4 zona teras mendapatkan temperatur tertinggi sebesar 1477 °C yang masih di bawah batasan temperatur di bola bahan bakar yaitu 1620 °C. Hasil yang diperoleh masih estimasi awal dan membutuhkan penelitian lebih lanjut dengan mempertimbangkan faktor-faktor lainnya seperti distribusi daya aksial dan radian yang lebih representatif, pengurangan aliran teras, dan kehilangan panas teras yang diserap oleh bejana reaktor.Kata kunci: Pebble bed, temperatur teras, RDE, RELAP5

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Section: Temperature Distribution For the 4 Core Zonesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Preliminary Analysis of Core Temperature Distribution of Experimental Power Reactor Using Relap5

et al. 2018

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“…HTR-10 dipilih karena memiliki tingkat keselamatan yang cukup baik dan menghasilkan energi yang besar sehingga dapat dimanfaatkan untuk proses kogenerasi. Selain itu, reaktor ini nantinya akan dikembangkan untuk memenuhi kebutuhan listrik di Indonesia [2], [7].…”

Section: Pendahuluanunclassified

Pengaruh Perisai Radiasi Pada Penyimpanan Kering Bahan Bakar Nuklir Bekas untuk Reaktor Daya Eksperimental

Artiani

Ratiko

Purwanto

et al. 2019

Jurnal Pengembangan Energi Nuklir

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PENGARUH PERISAI RADIASI PADA PENYIMPANAN KERING BAHAN BAKAR NUKLIR BEKAS UNTUK REAKTOR DAYA EKSPERIMENTAL Di masa mendatang, Badan Tenaga Nuklir Nasional (BATAN) berencana membangun Reaktor Daya Eksperimental (RDE) dengan daya termal 10 MW. RDE merupakan merupakan reaktor suhu tinggi dengan bahan bakar berupa pebble yang teknologinya mirip dengan reaktor HTR-10. Dalam operasional RDE hal yang perlu diperhatikan adalah pengelolaan Bahan Bakar Nuklir Bekas (BBNB). Oleh karena itu, teknologi pengelolaan BBNB HTR-10 dapat digunakan sebagai acuan dalam pengelolaan BBNB reaktor RDE. Pengelolaan BBNB reaktor HTR-10 disimpan dalam tangki penyimpanan dengan sistem kering. Telah dilakukan perhitungan laju dosis pada tangki penyimpanan BBNB di gedung reaktor dan interim storage menggunakan Monte Carlo N-Particle 5 (MCNP-5). Hasil perhitungan laju dosis pada tangki penyimpanan dengan berbagai ketebalan timbal (Pb) berkisar 11,7 – 2,560 x 106 µSv/jam dan 813,06 – 7,146 x 106 µSv/jam masing-masing pada gedung reaktor dan interim storage. Hal ini menunjukkan bahwa ketebalan Pb pada tangki penyimpanan tidak memberikan pengaruh yang signifikan dalam penurunan laju dosis baik pada gedung reaktor maupun interim storage. Penurunan laju dosis akan lebih efektif dengan penambahan Pb pada shielding luar tangki penyimpanan BBNB. Hasil perhitungan laju dosis berkisar 2,560 x 106 – 20,32 µSv/jam dan 7,146 x 106 – 105,58 µSv/jam untuk berbagai ketebalan Pb pada shielding luar tangki penyimpanan BBNB masing-masing di gedung reaktor maupun interim storage. Meskipun nilai laju dosis tidak memenuhi syarat Nilai Batas Dosis (NBD) bagi pekerja radiasi dan masyarakat, namun untuk keselamatan pekerja radiasi penanganan BBNB ini dapat diakomodir dengan konsep As Low As Resonably Achievable (ALARA), memperpanjang waktu peluruhan BBNB dan menfungsikan dinding interim storage sebagai shielding.Kata kunci : Reaktor Daya Eksperimental (RDE), Bahan Bakar Nuklir Bekas (BBNB), laju dosis, perisai radiasi.

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“…Constructon of non-commercial Experimental Power Reactors (RDE) leads to the technology type of Pebble Bed Reactor (PBR) -High Temperature Gas Cooled Reactor (HTGR). This type of reactor was chosen as it has very high safety features due to its passive safety features in the form of the ability to manage cooling performance without the need for external assistance and flexible applications, besides being able to generate electricity, it also produces high temperature steam which can be used for coal liquefaction, water desalination and water production [1]. The fuel used for PBR reactors is a kernel dispersed in spherical fuel elements.…”

Section: Introductionmentioning

confidence: 99%

“…In China, around 60 tons of graphite has been used for fuel of High Temperature Gas -Coooed Reactor (HTR) -10 and more than 1000 tons will be used for High Temperature Gas -Cooled Reactor Pebble-Bed Module (HTR-PM) [8]. It takes around 27000 PBR fuel for initial operation of RDE and 105 fuel per day to achieve steady state [1]. The need for graphite matrix per fuel is 0.2 kg so it takes about 156 tons of graphite for 20 years to operate 1 RDE with a capacity of 10 MW.…”

Section: Introductionmentioning

confidence: 99%

The Potential of Indonesian Graphite as Rde Fuel Matrix

Mustika

Sudirman

Fisli

et al. 2019

jsmi

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THE POTENTIAL OF INDONESIAN GRAPHITE AS RDE FUEL MATRIX. The development plan of Ex- perimental Power Reactor (RDE) in Indonesia is non-commercial and leads to the technology type of Pebble Bed Reactor (PBR) - High Temperature Gas Cooled Reactor (HTGR). The fuel used for PBR reactors is kernel dispersed in spherical fuel elements. The matrix used in PBR nuclear fuel is graphite which functions as a neutron moderator, fuel protective material and heat conductor. Domestication of the domestic fuel matrix needs to be conducted to improve national independence. Therefore, it is necessary to do research on the potential of local graphite to be used as RDE fuel matrix. This study focused on the identification and characterization of local and commercial graphite. The results are compared with the literature, how far it is fulfilling nuclear grade graphite for PBR fuel matrix. Characterization of graphite includes phase analysis with XRD, micro- structure with SEM, surface area/porosity, impurities determination with AAS, ICP-OES and NAA, equivalent boron content, carbon content, density, particle size distribution and ash content. The characterization results show that the carbon content obtained was 87.0 ± 4.2% for local graphite and 100% for commercial graphite. Meanwhile, for the purposes of nuclear graphite it requires a carbon content of >99%. The impurity content in local and commercial graphite still does not meet the RDE fuel matrix standard. The results of XRD analysis show that the local graphite phase is the same as the commercial graphite phase, namely the 2H graphite hexagonal crystal system with the lattice group of P 63/mmc. Particle size distribution and surface area of local graphite are higher compared to nuclear graphite literature. The ash content of commercial graphite was 0.236 ± 0.029 and local graphite was 9.587 ± 0.010%. The results of this study indicate that the local graphite from the flotation still requires a further refinement process to obtain local graphite that can be used as a fuel matrix for RDE.

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Cooling passive safety features of Reaktor Daya Eksperimental

Cited by 22 publications

References 9 publications

Preliminary Analysis of Core Temperature Distribution of Experimental Power Reactor Using Relap5

Preliminary Analysis of Core Temperature Distribution of Experimental Power Reactor Using Relap5

Pengaruh Perisai Radiasi Pada Penyimpanan Kering Bahan Bakar Nuklir Bekas untuk Reaktor Daya Eksperimental

The Potential of Indonesian Graphite as Rde Fuel Matrix

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