Preliminary Design Study of Small Power 30-50 MWt Experiment Power Reactor based on High Temperature Pebble Bed Gas Cooled Reactor Technology

Irwanto, Dwi; Permana, Sidik; Pramutadi, Asril; Pramuditya, Syeilendra

doi:10.1088/1742-6596/1127/1/012024

Cited by 10 publications

(9 citation statements)

References 4 publications

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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%

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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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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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“…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

et al. 2021

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“…These layers will keep the radioactive elements inside the fuel even in the event of an accident. Several studies regarding the neutronic review of the pebble bed-type HTGR and prismatic-type HTGR have been conducted (Irwanto et al, 2019;Pratama & Irwanto, 2020). The present study aimed to study the effect of the amount of coated fuel particles on the 25 MWt pebble-bed type HTGR reactor design using thorium fuel.…”

Section: Introductionmentioning

confidence: 99%

The Effects of the Number of Coated Fuel Particles on the Neutronic Aspects of 25 MWt Pebble Bed Reactor with Thorium Fuel

Irwanto

Yuningsih

2021

jppipa, pendidikan ipa, fisika, biologi, kimia

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High-Temperature Gas Reactor (HTGR) is a type of reactor that continues to be developed because of its advantages in terms of economic aspects, proliferation resistance, and safety aspects. One of the safety aspect improvements is due to the use of the Coated Fuel Particle (CFP). A coated fuel particle is a fuel with a diameter smaller than 1 mm and is protected by several carbon layers. In the Pebble Bed Reactor (PBR) type of HTGR design, the CFP is placed in a 6 cm fuel ball. How much CFP is put into the fuel ball will determine the neutronic characteristics of the reactor. In this study, the effect of the amount of CFP in the fuel ball on the 25 MWt PBR design using Thorium fuel and its impact on several important neutronic aspects, such as the effective multiplication factor, the amount of fuel enrichment, the utilization of fissile material, and the density of the fissile material formed. The calculation was performed by the Monte Carlo MVP / MVP-BURN code. This study found that the coated fuel particle fraction of 15% was the optimum value for the studied neutronic parameters.

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Preliminary Design Study of Small Power 30-50 MWt Experiment Power Reactor based on High Temperature Pebble Bed Gas Cooled Reactor Technology

Cited by 10 publications

References 4 publications

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

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

The Effects of the Number of Coated Fuel Particles on the Neutronic Aspects of 25 MWt Pebble Bed Reactor with Thorium Fuel

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