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European Programme on High Temperature Reactor Nuclear Physics, Waste and Fuel Cycle Studies

机译:欧洲高温反应堆核物理学,废料和燃料循环研究

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This project represents a collaborative R&D programme in the field of HTR-related nuclear physics, waste and fuel cycle studies (HTR-N) and is funded by the European Commission in the HTR-N and HTR-N1 contracts of the 5th Framework Programme (FP5). The paper illustrates the nuclear physics analyses of first criticality of the Japanese High-Temperature Test Reactor (HTTR) and of the Chinese 10 MWth High- Temperature Reactor (HTR-10). Reasons for discrepancies in the predictions of critical core configuration of HTTR are explained. Further activities deal with different fuel cycles aimed at effective burning of plutonium and minor actinides. First studies, for first generation plutonium (Pu-I) from reprocessed LWR uranium fuel, show that it is possible to reduce the fissile Pu content by up to 90%. Work continues on a symbiotic fuel cycle for LWR and HTR by burning of 2nd generation plutonium (Pu-II) from reprocessed spent LWR MOX fuel in an HTR core still maintaining HTR safety features with regard to nuclear stability and self-acting decay heat removal. Both, block-type and pebble fuel are analyzed. Studies on burnable poison and on uncertainties of nuclear data are included into the HTR-N programme. R&D on waste minimization options and experiments and first results on long-term behavior of spent HTR-fuel is reported, too.
机译:该项目代表了与第五框架计划的HTR-N和HTR-N1合同中的HTR相关核物理,废物和燃料循环研究领域的协作研发计划(HTR-N),并由欧洲委员会提供资金FP5)。本文说明了日本高温试验反应器(HTTR)和中国10 MWTH高温反应器(HTR-10)的第一临界性的核物理学分析。解释了HTTR的关键核心配置预测中差异的原因。进一步的活动处理不同的燃料循环,旨在有效地燃烧钚和轻微的散光。首先研究,对于来自再加工的LWR铀燃料的第一代钚(PU-I),表明可以将裂变PU含量降低至90%。通过在HTR核心再加工的钚(PU-II)中,在HTR核心的第二代钚(PU-II)燃烧,在核稳定性和自动衰减热除去的HTR安全功能中,继续在LWR和HTR的共生燃料循环中继续为LWR和HTR燃烧。分析了块型和卵石燃料。关于可燃毒药和核数据的不确定性的研究包括在HTR-N计划中。 R&D在废物最小化选项和实验中,也首先报告了花费HTR-燃料的长期行为的结果。

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