Development plan of high burnup fuel for high temperature gas-cooled reactors in future

Aihara, Jun; Ueta, Shohei; Honda, Masaki; Blynskiy, Petr; Gizatulin, Shamil; Sakaba, Nariaki; Tachibana, Yukio

doi:10.1080/00223131.2014.924886

Cited by 11 publications

(4 citation statements)

References 17 publications

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“…positive reactivity insertion, graphite corrosion, and potential breach in the radioactivity confinement [21]. Large amounts of air ingress or water ingress accident can be categorized as one of HTGR design extension conditions [22]. During air and/or water ingress accidents, the core temperature is a function of time.…”

Section: Controlling Chemical Attacksmentioning

confidence: 99%

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The Evaluation of the High Temperature Gas Cooled Reactor Safety to Fulfill the Requirement of the Next Generation Nuclear

Purba

Waskita

Tjahyani

2020

Jurnal Pengembangan Energi Nuklir

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THE EVALUATION OF THE HIGH TEMPERATURE GAS COOLED REACTOR SAFETY TO FULFILL THE REQUIREMENT OF THE NEXT GENERATION NUCLEAR. High temperature gas cooled reactor (HTGR) has been considered to be the most promising option to meet energy demands in the future. It has also been selected as the next generation nuclear plant. The primary safety requirement of the next generation nuclear plant design is to limit radioactive material releases to practically eliminate the need for public evacuation or sheltering beyond the exclusion area boundary. The purpose of this study is to evaluate the safety design of HTGRs in order to fulfill the requirement of the next generation nuclear plant. To achieve this objective, inherent safety features, fundamental safety functions, and confinement functions realized into the design of HTGRs are comprehensively evaluated. It is found that design provisions of HTGRs can fulfill the intention of keeping radionuclides at their original sources. The layers of the coated fuel particles are very robust to retain nuclear fission products for all foreseeable reactivity events. There will be no possibility of radioactive materials to be released even though related safety systems and operator intervention are not involved in the recovery actions. This design has complied with the requirement of the next generation nuclear plant, which is to practically eliminate the need for public evacuation or sheltering beyond the exclusion area boundary. ABSTRAK EVALUASI KESELAMATAN REAKTOR BERPENDINGIN GAS TEMPERATUR TINGGI DALAM MEMENUHI PERSYARATAN PEMBANGKIT NUKLIR MASA DEPAN.Reaktor berpendingin gas temperatur tinggi diprediksi akan menjadi pilihan yang menjanjikan untuk memenuhi kebutuhan energi masa depan. Persyaratan utama keselamatan bagi pembangkit nuklir masa depan adalah pembatasan pada lepasan material radioaktif sehingga secara praktis evakuasi dan sheltering diluar exclusion area boundary dapat dihilangkan. Tujuan penelitian ini adalah mengevaluasi desain keselamatan HTGR dalam memenuhi persyaratan pembangkit nuklir masa depan. Untuk mencapai tujuan ini maka fitur keselamatan melekat, fungsi keselamatan fundamental, dan fungsi pengungkungan yang diimplementasikan pada desain HTGR akan dievaluasi. Hasil evaluasi menunjukkan bahwa desain HTGR dapat mengungkung material radioaktif tetap berada pada sumbernya. Lapisan partikel bahan bakar mampu menahan produk fisi untuk setiap kejadian reaktifitas. Pelepasan material radioaktif tidak akan pernah terjadi meskipun intervensi sistem keselamatan dan operator tidak terlibat dalam aksi pemulihan. Dengan demikian, desain HTGR ini telah memenuhi persyaratan pembangkit nuklir masa depan yaitu tidak diperlukannya evakuasi dan shelter di luar exclusion area boundary. Kata kunci: Reaktor berpendingin gas temperatur tinggi, fitur keselamatan melekat, fungsi keselamatan fundamental, fungsi pengungkungan, pembangkit nuklir masa depan Keywords:high temperature gas cooled reactor inherent safety features fundamental safety functions confinement functions next gener...

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Section: Controlling Chemical Attacksmentioning

confidence: 99%

“…It also chemically and mechanically protects the SiC layer. In regard to fission product absorption, the buffer layer has a lower density than other three layers [22].…”

Section: Fuel Particle Coatingmentioning

confidence: 99%

The Evaluation of the High Temperature Gas Cooled Reactor Safety to Fulfill the Requirement of the Next Generation Nuclear

Purba

Waskita

Tjahyani

2020

Jurnal Pengembangan Energi Nuklir

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“…The particles typically comprise a spherical uranium‐based fuel kernel coated by a porous buffer carbon © layer, a denser pyrolytic C layer, a near theoretical density beta SiC (β‐SiC) layer, and finally, an additional layer of pyrolytic C 2 . The SiC coating layer provides structural support for the fuel particle and functions as a diffusion barrier for fission products migrating outward from the fuel kernel 3 . The particles are then compacted with a graphitic matrix material, into the form of cylindrical compacts or spherical pebbles for use in prismatic or pebble‐bed reactors, respectively.…”

Section: Introductionmentioning

confidence: 99%

High‐temperature oxidation behavior of the SiC layer of TRISO particles in low‐pressure oxygen

et al. 2023

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Surrogate tristructural-isotropic (TRISO)-coated fuel particles were oxidized in 0.2 kPa O 2 at 1200-1600 • C to examine the behavior of the SiC layer and understand the mechanisms. The thickness and microstructure of the resultant SiO 2 layers were analyzed using scanning electron microscopy, focused ion beam, and transmission electron microscopy. The majority of the surface comprised smooth, amorphous SiO 2 with a constant thickness indicative of passive oxidation. The apparent activation energy for oxide growth was 188 ± 8 kJ/mol and consistent across all temperatures in 0.2 kPa O 2 . The relationship between activation energy and oxidation mechanism is discussed. Raised nodules of porous, crystalline SiO 2 were dispersed across the surface, suggesting that active oxidation and redeposition occurred in those locations. These nodules were correlated with clusters of nanocrystalline SiC grains, which may facilitate active oxidation.These findings suggest that microstructural inhomogeneities such as irregular grain size influence the oxidation response of the SiC layer of TRISO particles and may influence their accident tolerance.

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“…However, the integrity and geometric shape of each layer are important for the safety and performance of the TRISO particle. Quality control of TRISO is extremely rigorous [4,5]. For example, temperature distribution is affected by layer thickness.…”

Section: Introductionmentioning

confidence: 99%

Three-Dimensional Measurement of TRISO Coated Particle Using Micro Computed Tomography

Zhu

Xiang

Peng

et al. 2019

Science and Technology of Nuclear Installations

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The fuel safety and performance of high-temperature gas-cooled reactor (HTGR) are dependent on the integrity and geometric parameter of Tri-structural Isotropic (TRISO) coated particle. Micro X-ray computed tomography (CT) was used for nondestructive testing and three-dimensional measurement of the particle components which are composed of kernel, buffer layer, inner pyrolytic carbon layer (IPyC), silicon carbide (SiC) layer, and outer pyrolytic carbon (OPyC) layer. The thickness distribution and volume of kernel and coating layers are obtained by constructing 3D volume rendering of TRISO particle. Mean thickness of each layer is calculated for comparison with design value. A comparison between two-dimensional and three-dimensional measurement results is also made. It is found that the thickness distribution of all layers approximately obeys Gaussian distribution. Deviation of the thickness of kernel and coating layers between 3D measurement result and design value is 7.88%, -25.63%, -45.50%, 13.87%, and 14.73%, respectively. The deviation will affect the failure probability of TRISO particle. Obvious difference of the OPyC mean thickness between 3D measurement and 2D measurement is found, which proves that the proposed 3D measurement provides comprehensive information of the particle. However, 2D and 3D measured thickness of the kernel and IPyC layer tend to be similar.

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Development plan of high burnup fuel for high temperature gas-cooled reactors in future

Cited by 11 publications

References 17 publications

The Evaluation of the High Temperature Gas Cooled Reactor Safety to Fulfill the Requirement of the Next Generation Nuclear

The Evaluation of the High Temperature Gas Cooled Reactor Safety to Fulfill the Requirement of the Next Generation Nuclear

High‐temperature oxidation behavior of the SiC layer of TRISO particles in low‐pressure oxygen

Three-Dimensional Measurement of TRISO Coated Particle Using Micro Computed Tomography

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