Helium leak and chemical impurities control technology in HTTR

Tochio, Daisuke; Shimizu, Atsushi; Hamamoto, Shoichiro; Sakaba, Nariaki

doi:10.1080/00223131.2014.921126

Cited by 6 publications

(2 citation statements)

References 2 publications

(1 reference statement)

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“…The major concerns for the commercialization of the HTGRs are the primary helium leakage and coolant chemistry during their operations. Tochio et al [16] confirmed that helium gas is easy to leak, especially at the elevated temperatures and pressures. Therefore, it is necessary to tightly control the possibility of the primary helium leakage to prevent the radioactive material releases into the environment.…”

Section: Helium Coolantmentioning

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 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: Helium Coolantmentioning

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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“…Although the obtained conclusions were constructive, the results were still insufficient to describe the chemical forms of FPs in the primary circuit environment. Some work focusing on the impurities in helium (He) that participate in chemical reactions indicated that these impurities should not be ignored [9][10][11]. The chemical reactions between radionuclides and gaseous impurities in the primary circuit should be clearly considered, and these radionuclides vary under different operating conditions.…”

Section: Introductionmentioning

confidence: 99%

Chemical Forms of Important Fission Products in Primary Circuit of HTR-PM under Conditions of Normal Operation and Overpressure and Water Ingress Accidents: A Study with a Chemical Thermodynamics Approach

Sun³

et al. 2019

Science and Technology of Nuclear Installations

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The chemical forms of important fission products (FPs) in the primary circuit are essential to the source term analysis of hightemperature gas-cooled reactors because the volatility, transfer, and diffusion of these radionuclides are significantly influenced by their chemical forms. Through chemical reactions with gaseous impurities in the primary circuit, these FPs exist in diverse chemical forms, which vary under different operational conditions. In this paper, the chemical forms of cesium (Cs), strontium (Sr), silver (Ag), iodine (I), and tritium in the primary circuit of the Chinese pebble-bed modular high-temperature gas-cooled reactor (HTR-PM) under normal conditions and accident conditions (overpressure and water ingress accident) are studied with chemical thermodynamics. The results under normal conditions show that Cs exists mainly in the form of Cs 2 CO 3 at 250 ∘ C and gaseous form at 750 ∘ C, and for I and Ag, Ag 3 I 3 and Ag convert to gaseous CsI and AgO, respectively, with increasing temperature, while SrCO 3 is the only main kind of compound for Sr. It is also observed that new compounds are generated under accidents: I exists in HI form when a water ingress accident occurs. Regarding tritium, the chemical forms of FPs change little, but compounds need higher temperature to convert. Furthermore, hazard of some FPs in different chemical forms is also discussed comprehensively in this paper. This study is significant for understanding the chemical reaction mechanisms of FPs in an HTR-PM, and furthermore it may provide a new point of view to analyze the interaction between FPs and structural materials in reactor as well as their hazards.

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Monte Carlo simulation of activity concentration measurement of primary coolant of high-temperature gas-cooled pebble-bed modular reactor

Lou

et al. 2020

Annals of Nuclear Energy

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Helium leak and chemical impurities control technology in HTTR

Cited by 6 publications

References 2 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

Chemical Forms of Important Fission Products in Primary Circuit of HTR-PM under Conditions of Normal Operation and Overpressure and Water Ingress Accidents: A Study with a Chemical Thermodynamics Approach

Monte Carlo simulation of activity concentration measurement of primary coolant of high-temperature gas-cooled pebble-bed modular reactor

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