Preliminary Study of 20 MWth Experiment Power Reactor based on Pebble Bed Reactor

Irwanto, Dwi; Permana, Sidik; Pramuditya, Syeilendra

doi:10.1088/1742-6596/877/1/012058

Cited by 7 publications

(8 citation statements)

References 6 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

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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

“…Digunakan total 100.000 neutron dengan 10 skip batches pada perhitungan dengan menggunakan MVP/MVP-BURN. Metodologi yang sama telah dikerjakan dan dibuktikan pada penelitan sebelumnya [9,12,18].…”

Section: Spesifikasi Desain Teras Reaktorunclassified

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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“…Some key parameters that contributed significantly have been investigated such as fissile enrichment, pebble bed fuel speed, fuel loading scheme, burn‐up performance as well as criticality condition. Those parameters are also can be used for the present evaluation 18,19 …”

Section: Design Conceptmentioning

confidence: 99%

“…Those parameters are also can be used for the present evaluation. 18,19 The studied HTGR design is based on a prismatic HTTR. The thermal output is ranging from 50 to 100 MWt.…”

Section: Design Concept 21 | Design Parametermentioning

confidence: 99%

Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power

Miftasani

Su’ud

Irwanto

et al. 2021

Intl J of Energy Research

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Summary The use of zirconium carbide (ZrC) as a substitute for silicon carbide (SiC) has been proposed to improve the performance of coated particles for high‐temperature gas‐cooled reactor (HTGR) fuel. Irradiation test on ZrC has proved that it has excellent characteristics for HTGR fuel compared with SiC, such as fission product retention capabilities and better resistance on fission product corrosion. Neutronic analysis on 30 MWt HTGR using ZrC and SiC has been performed in many previous studies. The research presented in this paper was conducted as a further continuation of the aforementioned studies. The present study was directed to analyze tristructural isotropic (TRISO)‐coated particles with ZrC as a substitute for the SiC layer on an HTGR with different power rates. Here, we used high‐temperature test reactor design, an experimental scale prismatic HTGR built and operated in Japan. The power was varied at the range of 50‐100 MWt, while the reactor geometry was modified by applying an additional fuel layer in the axial and radial directions. Neutronic analysis of the reactor was investigated by calculating the k‐eff, k‐inf, power peaking factor, burn‐up level, neutron spectrum, and Doppler effect using ZrC and SiC layers for TRISO‐coated fuel particles. The result shows the coated fuel particle using the ZrC layer has the same performance as SiC with an insignificant difference in the values on neutronic aspects calculation. Neutronic calculations are performed using the SRAC code with the Japanese Evaluated Nuclear Data Library 4.0 nuclear data library.

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“…The main HTGR model comes in a variety of fuel cycles, designs, and variants. The current reactors can use highly enriched uranium, 24,25 high-assay low enriched uranium, 26,27 or low enriched uranium with thorium as the fertile material. 28 Plutonium 23,25 can be used as a fissile driver in thorium-based fuels, as well as U-233 from other reactors.…”

Section: Introductionmentioning

confidence: 99%

A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor

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Preliminary Study of 20 MWth Experiment Power Reactor based on Pebble Bed Reactor

Cited by 7 publications

References 6 publications

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

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

Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power

A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor

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