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Research on graphite powders used for HTR-PM fuel elements

Rare Metals 2006年第Z1期25卷 347-350页

作者： ZHAO Hongsheng LIANG Tongxiang ZHANG Jie LI Ziqiang TANG Chunhe Institute of Nuclear and New Energy Technology Tsinghua University Beijing 100084 China Institute of Nuclear and New Energy Technology Tsinghua University Beijing 100084 China Institute of Nuclear and New Energy Technology Tsinghua University Beijing 100084 China Institute of Nuclear and New Energy Technology Tsinghua University Beijing 100084 China Institute of Nuclear and New Energy Technology Tsinghua University Beijing 100084 China

Different batches of natural graphite powders and electrographite powders were characterized by impurity, degree of graphitization, particle size distribution, specific surface area, and shape characteristics. The graphite balls consist of proper mix-ratio of natural graphite, electrographite and phenolic resin were manufactured and characterized by thermal conductivity, anisotropy of thermal expansion, crush strength, and drop strength. Results show that some types of graphite powders possess very high purity, degree of graphitization, and sound size distribution and apparent density, which can serve for matrix graphite of HTR-PM. The graphite balls manufactured with reasonable mix-ratio of graphite powders and process method show very good properties. It is indicated that the properties of graphite balls can meet the design criterion of HTR-PM. We can provide a powerful candidate material for the future manufacture of HTR-PM fuel elements.

关键词： high temperature gas-cooled reactor graphite powder design criterion

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Thermochemical Water Splitting for Hydrogen Production Utilizing Nuclear Heat from an HTGR

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Tsinghua Science and Technology 2005年第2期10卷 270-276页

作者：吴莘馨 ONUKI Kaoru Institute of Nuclear and New Energy Technology Tsinghua University Beijing 100084 China Japan Atomic Energy Research Institute Ibaraki 311-1394 Japan

A very promising technology to achieve a carbon free energy system is to produce hydrogen from water, rather than from fossil fuels. Iodine-sulfur (IS) thermochemical water decomposition is one promising process. The IS process can be used to efficiently produce hydrogen using the high temperature gas-cooled reactor (HTGR) as the energy source supplying gas at 1000℃. This paper describes that dem- onstration experiment for hydrogen production was carried out by an IS process at a laboratory scale. The results confirmed the feasibility of the closed-loop operation for recycling all the reactants besides the water, H2, and O2. Then the membrane technology was developed to enhance the decomposition efficiency. The maximum attainable one-pass conversion rate of HI exceeds 90% by membrane technology, whereas the equilibrium rate is about 20%.

关键词： high temperature gas-cooled reactor hydrogen production thermochemical water splitting

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维普期刊数据库

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Research on the Silicon Carbide Layer of Coated Fuel Particles

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Tsinghua Science and Technology 1996年第1期1卷 45-49页

作者：徐世江杨冰朱钧国张秉忠张冬梅张纯 Institute of Nuclear Energy Technology Tsinghua University Beijing 100084

The 10MW high temperature gas-cooled test reactor (HTR-10) under construction at INET uses whole ceramic fuel elements. The main barrier which prevents fission product release is the SiC layer of the coated fuel particles. Fabrication of high quality SiC layers is one of the key R&D tasks for the HTR-10 fuel element. The SiClayer was deposited on the fuel particles in a 50 mm conical fluidized bed using the CVD (chemical vapour deposition) technique. The density, thickness, strength and elastic modulus of the SiC layer were measured. The microstructure was observed using SEM (scanning electron microscope ). Parameters were established for manufacturing the SiC layer of the coated fuel particles to be used in the HTR-10. It was found that the traditional density measurement by the sink-float method is questionable in the low density region and that the SiC layer may be contaminated by uranium under certain conditions.

关键词： high temperature gas-cooled reactor fuel element coated fuel particle SiC density strength microstructure uranium contamination

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