Equilibrium Core Design of <i>Reaktor Daya Eksperimental</i>

Setiadipura, Topan; Suwoto, Suwoto; Zuhair,

doi:10.1088/1742-6596/1198/2/022076

Cited by 4 publications

(6 citation statements)

References 7 publications

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“…Beberapa penelitian mengenai tinjauan neutronik pada HTGR tipe pebble bed serta penggunaan CFP telah dilakukan [7][8][9]. Tujuan dari penelitian ini adalah untuk mempelajari pengaruh fraksi CFP terhadap beberapa parameter penting neutronik seperti faktor multiplikasi efektif, spektrum energi neutron, densitas material fertil dan fisil serta utilisasi material fisil pada desain HTGR tipe pebble bed berdaya 40 MWt dengan elemen bakar uranium, kemudian mencari nilai optimal jumlah CFP yang dapat digunakan.…”

Section: Pendahuluanunclassified

Studi Pengaruh Fraksi Coated Fuel Particle pada Desain Pebble Bed Reactor 40 MWt Berbahan Bakar Uranium

Irwanto

Yuningsih

2021

Jurnal Pengembangan Energi Nuklir

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Coated Fuel Particle (CFP) adalah tipe elemen bakar mikro berdiameter lebih kecil dari 1 mm, yang di dalamnya terdapat material fisil yang dilapisi oleh beberapa lapisan karbon. Pebble Bed Reactor (PBR) menggunakan konsep CFP untuk elemen bakarnya. CFP dimasukan ke dalam bola elemen bakar berukuran 6 cm dan disebar di dalam zona elemen bakar. Tujuan penelitian ini adalah untuk mempelajari pengaruh dari fraksi CFP terhadap beberapa parameter neutronik penting seperti faktor multiplikasi efektif, spektrum energi neutron, perubahan densitas material fisil dan fertil, serta tingkat utilisasi material fisil. Analisa dilakukan untuk pada sistem PBR berdaya 40 MWt dengan menggunakan kode Monte Carlo MVP/MVP-BURN, dengan fraksi CFP yang dianalisa berkisar antara 5-60%. Dari penelitian ini didapatkan bahwa fraksi CFP sebesar 10% memberikan nilai optimal untuk beberapa parameter neutronik terkait dan dapat dijadikan acuan untuk desain Pebble Bed Reactor berdaya 40 MWt dengan elemen bakar uranium.

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Section: Pendahuluanunclassified

Studi Pengaruh Fraksi Coated Fuel Particle pada Desain Pebble Bed Reactor 40 MWt Berbahan Bakar Uranium

Irwanto

Yuningsih

2021

Jurnal Pengembangan Energi Nuklir

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“…As mentioned in Table 2, pebble fuel is divided into regions. The outer region is the graphite shell with a thickness of 0.5cm, the density of this graphite is 1.73 g/cm 3 [4]. And the inner region, called fuel zone, is a 2.5cm sphere in which ~8335 TRISO coated fuel particle is dispersed randomly with a packing fraction of 0.050248 [ [15].…”

Section: Pebble Fuelmentioning

confidence: 99%

“…Based on the above positioning pattern, different fill function is assigned to simulate the pebble fuel or pebble moderator. Pebble fuel is assigned for 57% of the first id while the rest particle-ids are assigned as pebble moderator [4]. Using this strategy, we can assure that a randomly mixed composition between fuel pebble and moderator is achieved.…”

Section: Pebble Bed Corementioning

confidence: 99%

“…For that reason, as part of the national development program [3], a PBR design development called Reaktor Daya Eksperimental was developed by the National Nuclear Energy Agency (BATAN). Equilibrium and safety analysis of RDE was performed using a finite difference based analysis with a specific method to model the fuel movement in the core [2] [4]. A Monte Carlo (MC) based analysis for a Once-Through-Then-Out (OTTO) fuel refueling of PBR called MCPBR [5] is already developed.…”

Section: Introductionmentioning

confidence: 99%

“…Criticality analysis is traditionally used as an initial check for a particular code or method's modeling capability. HTR-10, which already got its first criticality since 2000 [4] becoming the common object to be analyzed. The initial calculation from the Institute of Nuclear Energy Technology (INET), which designed and constructed the HTR-10, was using VSOP94 code [7], a diffusion calculation code.…”

Section: Introductionmentioning

confidence: 99%

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Criticality Analysis of HTR-10 using an Open Source Monte Carlo code OpenMC

Mahfudin

Setiadipura

2020

Jurnal Pengembangan Energi Nuklir

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As one of advance nuclear reactor design, capability to model and analyze the pebble bed reactor is important. Availability and capability of an accurate open source and open access software for pebble bed reactor analysis is strategic. It can broaden the involvement of more student and researcher which finally may improve the research and development in this field. Current study aim to develop the pebble bed core model and perform a criticality study of HTR-10 core design. This study exploit the capability of openMC software to model a double heterogenety geometry using a TRISO Pack Model Building based on random sequential packing and closed random packing. Physical parametric surveys of the developed model show an expected results in which the model able to reflect the negative reactivity feedback of HTR-10 design. The critical height of HTR-10 model with helium from current model, VSOP, and MCNP are 125.881 cm, 125.804 cm, 126.116 cm, respectively. A code-to-code criticality analysis comparison of current model with VSOP and MCNP code reported by INET shows a good comparison and suggest that current method can be used for further pebble bed analysis.

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