共查询到19条相似文献,搜索用时 93 毫秒
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随着我国核电事业的发展,乏燃料不断累积,核电乏燃料的安全管理已成为核工业持续发展不得不面临的重大难题."十四五"规划中也重点提出要建设乏燃料后处理厂的要求.针对日益严峻的乏燃料后处理要求,本文系统归纳总结了当前国内后处理技术发展现状、分析了乏燃料后处理技术发展趋势,并针对当前国内乏燃料发展中的问题,提出了相应的研究思路,为下一步乏燃料后处理发展提供指导. 相似文献
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安全高效发展核电是实现清洁能源发展目标的重要举措,而乏燃料长期安全管理一直是制约核电规模化发展的瓶颈之一。为了保障乏燃料后处理产业健康有序发展,应加快有关领域的立法工作,为我国乏燃料的科学管理提供制度保障。本文从我国乏燃料管理的现状出发,分析了该领域立法的必要性和可行性,并给出了有关建议。我国乏燃料管理领域立法应完善核法律法规体系,明确相关主体责任,进一步提高乏燃料管理基金利用效率,重视公众参与,切实保障我国核能可持续发展。 相似文献
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基于铀资源需求和乏燃料积累预测,论证了我国发展快堆闲式核燃料循环的必要性,通过国内外调研,重点对影响我国快堆闭式循环的三个关键因素:钚元素积累、快堆技术、乏燃料后处理及快堆燃料技术的现状进行分析,并提出了展望和建议。 相似文献
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China is leading the recent revival of nuclear energy programs. The Chinese government plans to increase nuclear generating capacity to 40 GWe by 2020, while the installed capacity is 8.6 GWe in 2007. In view of the enthusiasm shown for nuclear electricity throughout the country, the actual scale of Chinese nuclear power development is expected to reach 70 GWe by 2020. However, the low cost proven uranium reverses (cost category to <130 US $/kg) in China only meet half demand of 40 GWe capacity in 2020. And overlying China's increased demand is continued political sensitivity about the uranium trade. Meanwhile, the capacity of China's spent fuel reprocessing cannot keep up with the increasing spent fuel. And the legal administrative system of radioactive waste and spent fuel management is outdated. Hence it is proposed in this paper that the accelerated development of nuclear power industry is not good, and the over-accelerated development may be harmful, without appropriately considering the uranium resources and spent fuel management. 相似文献
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Although China's nuclear power industry is relatively young and the management of its spent nuclear fuel is not yet a concern, China's commitment to nuclear energy and its rapid pace of development require detailed analyses of its future spent fuel management policies. The purpose of this study is to provide an overview of China's fuel cycle program and its reprocessing policy, and to suggest strategies for managing its future fuel cycle program. The study is broken into four sections. The first reviews China's current nuclear fuel cycle program and facilities. The second discusses China's current spent fuel management methods and the storage capability of China's 13 operational nuclear power plants. The third estimates China's total accumulated spent fuel, its required spent fuel storage from present day until 2035, when China expects its first commercialized fast neutron reactors to be operational, and its likely demand for uranium resources. The fourth examines several spent fuel management scenarios for the present period up until 2035; the financial cost and proliferation risk of each scenario is evaluated. The study concludes that China can and should maintain a reprocessing operation to meet its R&D activities before its fast reactor program is further developed. 相似文献
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《Journal of power sources》2002,105(2):250-255
Electronic devices show an ever-increasing power demand and thus, require innovative concepts for power supply. For a wide range of power and energy capacity, membrane fuel cells are an attractive alternative to conventional batteries.The main advantages are
- •the flexibility with respect to power and capacity achievable with different devices for energy conversion and energy storage,
- •the long lifetime and long service life,
- •the good ecological balance,
- •very low self-discharge.
- •the much higher power density for hydrogen fuel cells,
- •the higher energy density per weight for the liquid fuel,
- •safety aspects and infrastructure for fuel supply for hydride materials.
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Economic growth in East Asia has rapidly increased regional energy, and especially, electricity needs. Many of the countries of East Asia have sought or are seeking to diversify their energy sources and bolster their energy supply and/or environmental security by developing nuclear power. Rapid development of nuclear power in East Asia brings with it concerns regarding nuclear weapons proliferation associated with uranium enrichment and spent nuclear fuel management. This article summarizes the development and analysis of four different scenarios of nuclear fuel cycle management in East Asia, including a scenario where each major nuclear power user develops uranium enrichment and reprocessing of spent fuel individually, scenarios featuring cooperation in the full fuel cycle, and a scenario where reprocessing is avoided in favor of dry cask storage of spent fuel. The material inputs and outputs and costs of key fuel cycle elements under each scenario are summarized. 相似文献
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Sumit Basu Moiz Diwan Mohamad G. Abiad Yuan Zheng Osvaldo H. Campanella Arvind Varma 《International Journal of Hydrogen Energy》2010
Ammonia borane (AB) and sodium borohydride (SBH) are candidate materials for on-board hydrogen storage that can be dehydrogenated upon demand. The rheological properties of the dehydrogenated by-products are important to quantify their removal and transportability from the hydrogen storage system. This paper presents visco-elastic property (elastic stiffness and viscous damping) measurements of the spent fuels obtained from AB hydrolysis, hydrothermolysis and thermolysis; and SBH hydrolysis. Smaller stiffness and larger mobility (or smaller viscous damping) indicate better transportability of the spent fuel. In addition, flow property (dynamic angle of repose and avalanching time) measurements for the hydrolysis spent fuels of AB and SBH are also presented. Comparing with the SBH hydrolysis spent fuel, the AB hydrolysis spent fuel had a lower stiffness and larger mobility, as well as lower angles of dynamic repose and avalanche power peaks, indicating that it is more transportable. Among all the investigated AB spent fuels in the present study, those obtained from its neat thermolysis (at 120 °C) and hydrothermolysis (40–70 wt%) were found to be the most transportable, followed by-products of its hydrolysis and ionic solvent-aided thermolysis, respectively. 相似文献
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K.C. Chen K. Ting Y.C. Li Y.Y. Chen W.K. Cheng W.C. Chen C.T. Liu 《International Journal of Pressure Vessels and Piping》2010
Due to the large power supply in the energy market since 1960s, the nuclear power planets have been consistently constructed throughout the world in order to maintain and supply sufficient fundamental power generation. Up to now, most of the planets have been operated to a point where the spent fuel pool has reached its design capacity volume. To prevent the plant from shutdown due to the spent fuel pool exceeding the design capacity, the dry cask storage can provides a solution for both the spent fuel pool capacity and the mid-term storage method for the spent fuel bundles at nuclear power planet. 相似文献