Radiation damage of graphite in fission and fusion reactor systems

Engle, Genevieve; Kelly, Brian

doi:10.1016/0022-3115(84)90582-8

Cited by 23 publications

(3 citation statements)

References 6 publications

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“…There are known challenges with the use of graphite in nuclear applications. However, graphite reflectors have been found to have lower activity and produce lower nuclear heat than the commonly used Be multipliers, but due to long-lived 14 C and 36 Cl, production graphite usage has to be quantified for the individual scenario [26], [27], [28]. Similarly, problems with He are well understood.…”

Section: Scylla© Blanket Conceptmentioning

confidence: 99%

Overview of Kyoto Fusioneering’s SCYLLA© (“Self-Cooled Yuryo Lithium-Lead Advanced”) Blanket for Commercial Fusion Reactors

Pearson¹,

Baus²,

Konishi³

et al. 2022

IEEE Trans. Plasma Sci.

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This article outlines Kyoto Fusioneering's (KF's) initial engineering and development activities for its self-cooled lithium lead-type blanket: Self-Cooled Yuryo Lithium-Lead Advanced (SCYLLA©). We provide details on overall design, including an initial tritium breeding ratio (TBR) assessment via neutronics analysis, as well as the status of SCYLLA©-relevant R&D. This includes silicon carbide composite (SiC f /SiC) manufacturing techniques, tritium extraction, materials compatibility, and heat transfer, which are being explored via collaboration with Kyoto University. Results of previous work in relation to this R&D are presented. Permeability coefficients indicate a promising property of SiC f /SiC tritium hermeticity at high temperatures. Tritium extraction technology via vacuum sieve tray (VST) is shown to be demonstrated at engineering scale. A local TBR of up to 1.4 can be achieved with the SCYLLA© configuration. Fabrication methods for various SiC f /SiC components including the blanket module, heat exchanger, and flow path components are provided. A tritium compatible high-temperature SiC f /SiC heat exchanger is discussed. Commercial viability and reactor adaptability are considered as a theme throughout. Finally, KF's plans to build a facility for demonstration reactor relevant testing of a SCYLLA© prototype in the mid-2020s, which will provide a significant step toward commercial fusion energy, are presented.

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Section: Scylla© Blanket Conceptmentioning

confidence: 99%

Overview of Kyoto Fusioneering’s SCYLLA© (“Self-Cooled Yuryo Lithium-Lead Advanced”) Blanket for Commercial Fusion Reactors

Pearson¹,

Baus²,

Konishi³

et al. 2022

IEEE Trans. Plasma Sci.

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“…Важным свойством является то, что толерантность плазмы к примесям из углеродных материалов с низким атомным номером намного выше, по отношению к другим твердым конструкционным материалам. Высокая устойчивость графита к тепловому воздействию обеспечивает уникальные варианты конструкции внутрикамерных элементов, а низкое поперечное сечение захвата нейтронов в сочетании с очень низкой активацией может значительно облегчить проблемы технического обслуживания термоядерного реактора, проблему утилизации отходов, охраны окружающей среды и безопасности [6].…”

Section: Introductionunclassified

Experiments on Desorption of Atmospheric Gases From Graphite Elements of the KTM Tokamak's First Wall

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Гордиенко

et al. 2021

jour

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This article describes the preparation and conduct of experiments on atmospheric gas release from graphite elements (tiles) of the KTM tokamak during their heating to a temperature of 450-480 °С. The paper describes the design of the experimental device used for thermal desorption experiments with graphite tiles of the KTM. The method of conducting thermal desorption experiments is described. The time dependence of gas release from graphite tiles during their annealing at linear heating at a rate of 3.5 °C/min to a temperature of 450-480 °C in the constant pumping mode with a high-vacuum pump are given. A brief analysis of experimental data is presented. Recommendations on the technology of preparing graphite tiles before their mounting in the vacuum chamber of the KTM tokamak are proposed.

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“…High temperature and neutron irradiation on the graphite can result in various radiation damage defects and structural changes on graphite material. High temperature will accelerate the radiation damage, so the graphite in the VHTR must not undergo a very fast structural change which could have an unexpected impact on the operation of entire nuclear reactor system [3].…”

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Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure

Pinhero

Windes

2015

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The fast particle radiation damage effect of graphite, a main material in current and future nuclear reactors, has significant influence on the utilization of this material in fission and fusion plants. Atoms on graphite crystals can be easily replaced or dislocated by fast protons and result in interstitials and vacancies. The currently accepted model indicates that after most of the interstitials recombine with vacancies, surviving interstitials form clusters and furthermore gather to create loops with each other between layers. Meanwhile, surviving vacancies and interstitials form dislocation loops on the layers. The growth of these inserted layers cause the dimensional increase, i.e. swelling, of graphite. Interstitial and vacancy dislocation loops have been reported and they can easily been observed by electron microscope. However, observation of the intermediate atom clusters becomes is paramount in helping prove this model. We utilize fast protons generated from the University of Missouri Research Reactor (MURR) cyclotron to irradiate highlyoriented pyrolytic graphite (HOPG) as target for this research. Post-irradiation examination (PIE) of dosed targets with high-resolution transmission electron microscopy (HRTEM) has permit observation and analysis of clusters and dislocation loops to support the proposed theory. Another part of the research is to validate M.I. Heggie's Ruck and Tuck model, which introduced graphite layers may fold under fast particle irradiation. Again, we employed microscopy to image irradiated specimens to determine how the extent of Ruck and Tuck by calculating the number of folds as a function of dose. Our most significant accomplishment is the invention of a novel class of high-intensity pure beta-emitters for long-term lightweight batteries. We have filed four invention disclosure records based on the research conducted in this project. These batteries are lightweight because they consist of carbon and tritium and can be fabricated to conform to many geometric shapes. In addition, we have published eight peer-reviewed American Nuclear Society (ANS) transactions, and presented our findings at ANS National Meetings, and several universities. BACKGROUND: The increasing demand of energy has lead to the current energy security crisis. Despite significant pressures to decrease the production and use of fossil fuel, most of the fastgrowing energy demand is still being satisfied by fossil fuel. Some of these pressures are founded in environmental concerns like significant air pollution, for example, dust, heavy metals, NO x and SO x ; and the generally accepted global warming problem caused by the production and release of greenhouse gases. In order to solve the energy crisis in an environmental friendly way, a clean and sustainable energy is needed. Many renewable energy solutions, such as tidal, wind and solar have varying limitations and thus are not able to provide continuous electricity continuously and reliably. Hydropower has strict demand on terrain, specifically the potential ene...

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Radiation damage of graphite in fission and fusion reactor systems

Cited by 23 publications

References 6 publications

Overview of Kyoto Fusioneering’s SCYLLA© (“Self-Cooled Yuryo Lithium-Lead Advanced”) Blanket for Commercial Fusion Reactors

Overview of Kyoto Fusioneering’s SCYLLA© (“Self-Cooled Yuryo Lithium-Lead Advanced”) Blanket for Commercial Fusion Reactors

Experiments on Desorption of Atmospheric Gases From Graphite Elements of the KTM Tokamak's First Wall

Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure

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