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本文根据聚变-裂变混合能源堆方案设计和燃料组件功率分布的特点,利用自主开发的蒙卡-燃耗耦合程序,开展了详细的燃料管理方案设计研究,分别设计了整体后处理的燃料管理方案、双循环燃料管理方案以及分批燃料管理方案,针对这些类型的燃料管理方案,进行了燃耗分析计算,研究了各种燃料管理方案下各区燃耗及主要裂变核素成分随燃耗的变化。根据各燃料管理方案的主要特点和计算分析结果,对比总结了它们的优点和缺点。本文为今后的聚变-裂变混合能源堆提供了燃料管理上的建议,也为进一步的经济性分析优化研究打下了基础。 相似文献
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本文用数值计算法计算了聚变-裂变混合堆燃料元件包壳的热应力分布。计算结果表明由D-T周期性燃烧引起的交变热应力比裂变堆稳态运行的热应力问题严酷得多。热应力的变化规律与温度循环范围及包壳的壁厚成正比。保证安全可靠运行的关键是合理设计热循环的温度范围。 相似文献
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对聚变-裂变混合堆的安全性进行了初步分析和探讨。主要利用改进后的混合堆放射性程序FDKR对混合堆产生的核废物及放射性进行计算,并将结果与压水堆、高温气冷堆和液态金属冷却快中子增殖堆进行了比较。结果表明,混合堆与裂变动力堆相比有较好的安全性。 相似文献
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轻水堆乏燃料和钍燃料的利用是解决乏燃料后处理问题和核燃料短缺的有效途径之一。本工作以ACR-700标准燃料为参考,研究了4种不同混合比例的轻水堆乏燃料及钍燃料在ACR-700中的k∞和燃耗。研究结果表明,将裂变产物分离后,轻水堆乏燃料的重锕系核素在ACR-700中可作为一很好的燃料;只要加入足够的启动燃料,钍燃料也可作为很好的转换燃料,使反应堆内生成233U的速率大于易裂变燃料的消耗速率,233U的生成对反应堆运行后期维持临界起重要作用。 相似文献
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关于我国核燃料闭合循环战略的讨论 总被引:1,自引:0,他引:1
按我国《核电中长期发展规划(2005—2020年)》,我国将坚持核燃料闭合循环的技术路线。讨论了实施核燃料闭合循环的意义,简要介绍了国际发展的基本态势。对几个相关问题,如商用乏燃料处理厂建设时机;钚的产用平衡;MOX燃料在热堆核电站使用的适应性;经济性等作了讨论,并提出政策建议。 相似文献
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随着我国大型遗留核燃料后处理设施退役治理工作的按序推进,现已进入退役关键阶段,为使其中强放射性区域安全、顺利实施退役,研究、摸索和掌握远距离操作应用技术,良好的退役设计与策划,是推进退役事业、使之具备工作条件和能力的先决条件。由于我国尚未建立乏燃料后处理厂退役用远距离操作的相关标准体系,本文首次依据对我国遗留后处理厂现状特点,深入剖析典型退役难点,并参照国外同类型工程远距离操作经验提出了退役用远距离操作的总体设计要求,可以作为设计远距离操作技术决策的重要依据。 相似文献
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Robert D. Mariani 《Journal of Nuclear Materials》2010,404(1):25-32
Spent metallic nuclear fuel is being treated in a pyrometallurgical process that includes electrorefining the uranium metal in molten eutectic LiCl-KCl as the supporting electrolyte. We report a model for determining the density of the molten salt. Material balances account for the net mass of salt and for the mass of actinides present. It was necessary to know the molten salt density, but difficult to measure. It was also decided to model the salt density for the initial treatment operations. The model assumes that volumes are additive for the ideal molten salt solution as a starting point; subsequently, a correction factor for the lanthanides and actinides was developed. After applying the correction factor, the percent difference between the net salt mass in the electrorefiner and the resulting modeled salt mass decreased from more than 4.0% to approximately 0.1%. As a result, there is no need to measure the salt density at 500 °C for inventory operations; the model for the salt density is found to be accurate. 相似文献
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核燃料循环成本与核电的竞争力 总被引:3,自引:0,他引:3
国际市场核燃料价格变幻莫测,对我国核电的成本和发展产生影响,本文提出了控制整个核燃料循环成本的设想,以提升中国核电的竞争力,促进核燃料产业和核电产业的共同发展。 相似文献
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Hee Seo Seong-Kyu Ahn Bo-Young Han Chaehun Lee Hee-Sung Shin Bong Young Kim 《Journal of Nuclear Science and Technology》2016,53(10):1563-1572
A simple and fast method of nuclear material accountancy of pressurized water reactor (PWR) UO2 spent fuel rods for safeguards application was developed utilizing the isotope correlation between the amounts of 137Cs and total Pu. To this end, the following steps were taken: (1) as much destructive analysis (DA) data as possible for segments taken from a PWR UO2 spent fuel rod were aggregated from publicly available data sources; (2) the DA data were corrected so as to have the same cooling time (i.e., CT = 0 y) and analyzed for outliers; (3) an equation converting the 137Cs amount to the Pu amount was obtained by regression analysis with logarithmic curve fitting; and (4) the error in determining the Pu amount was evaluated for the imposition of a limit on the range of burnup (BU) or initial enrichment (IE). It was found that the averaged % error in calibration was determined to be 3.88% ± 2.68% (= mean ± 1 standard deviation) for the BU range over 30 GWd/tU and falling with increasing BU range. On the other hand, there was no benefit in applying the limit of the IE range. Lastly, the Pu-mass difference between various methods was compared and it was found that the difference can be incurred up to 11.4%, according to the choice of method. In conclusion, the proposed isotope correlation technique could be used for input material accountancy with reasonable uncertainty. 相似文献
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HUOXiao-Dong XIEZhong-Sheng 《核技术(英文版)》2004,15(3):183-187
High neutron economy, on line refueling and channel design result in the unsurpassed fuel cycle flexi-bility and variety for CANDU reactors. According to the Chinese national conditions that China has both PWR and CANDU reactors and the closed cycle policy of reprocessing the spent PWR fuel is adopted, one of the advanced nu-clear fuel cycles of PWR/CANDU synergism using the reprocessed uranium of spent PWR fuel in CANDU reactor is proposed, which will save the uranium resource (-22.5%), increase the energy output (-41%), decrease the quantity of spent fuels to be disposed (-2/3) and lower the cost of nuclear poower, Because of the inherent flexibility of nuclearfuel cycle in CANDU reactor, and the low radiation level of recycled uranium(RU), which is acceptable for CANDU reactor fuel fabrication, the transition from the natural uranium to the RU can be completed without major modifica-tion of the reactor core structure and operation mode.It can be implemented in Qinshan Phase Ⅲ CANDU reactors with little or no requirement of big investment in new design. It can be expected that the reuse of recycled uranium of spent PWR fuel in CANDU reactor is a feasible and desirable strategy in China. 相似文献
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Tetsuo Ikegami 《Progress in Nuclear Energy》2005,47(1-4):231-238
This paper presents fast reactor core concept and its feasibility as a part of newly proposed compound process fuel cycle in which spent fuels of light water reactor are multi-recycled without conventional reprocessing but with only pyrochemical processing, fuel re-fabrication and reloading to the fast reactor core. Results of the core survey analyses in order to find out the feasibility of this concept, taking example for BWR MOX spent fuel of 60 GWd/t burn-up, show that four times recycling of LWR spent fuel with the burn-up of more than 300 GWd/t can be achieved without increasing MA content. Such benefits will be expected in this concept as reduction of fuel cycle cost due to simplified reprocessing procedure, reduction of environmental impacts due to reduced high level waste, efficient utilization of nuclear fuel resources, enhancement of nuclear non-proliferation, and suppression of LWR spent fuel pile-up. 相似文献