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以中子诱发235U裂变产生的135Xe 的累积产额数据为例, 利用了所有可利用的实验数据, 介绍了裂变产物产额数据的评价方法, 包括数据的收集、 修正、 评价、 误差调整和数据处理, 特别是协方差数据的评价、 半经验模型理论计算数据的应用和相关数据的处理, 给出了135Xe热能点产额的推荐值以及0~20 MeV产额-能量关系曲线。 Takeing 135Xe produced by neutron induced fission of 235U as an example, the evaluation method for fission yield was introduced using the all experimental data available. The evaluation procedure includes the experimental data collection, correction, evaluation, error assessment and data analysis. The study of the uncertainty covariance, application of semi empirical theoretical calculation and the yield energy dependence of 135Xe in the incident energy range 0~20 MeV were emphasized in this work.  相似文献   
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本模型基于裂变多通道无规颈断裂模型,考虑宏观液滴能、壳效应能以及壳效应与温度的关系,得到参数化的势能表示形式。通过拟合不同测量方法得到的实验数据(经过评价) 获得3 组模型参数。3 组参数计算的碎片质量分布均很好地再现了不同能点的实验数据,除了基于动能法实验数据得到的参数外,其14 MeV的计算结果与实验数据符合较差。研究发现,不同入射中子能量的裂变碎片质量分布有4 个主要交叉点,在叉点之上的产额随入射中子能量增加减少,之下的产额则随入射中子能量上升;内侧(或外侧) 的两个交叉点质量数之和近似等于裂变复合核的质量数;不同裂变系统的重峰左侧的交叉点都保持在132 附近。Present model was based upon Brosa model, where macro energy,shell effect energy and its decreasing with system temperature were considered and parameterized. 3 sets of model parameters were obtained by fitting to 3 groups of evaluated experimental data, respectively, where the groups were classified by measured method: radiochemistry (RA) method, double kinetic energy (KE) method, and both (ALL). All the 3 sets of parameters could well reproduce themeasured mass distributions on different energies, except the KE set on 14 MeV. The result shows the mass distributions mainly had 4 trend turning points, above which the yield decreasing and below which the yield increasing with energy.The sum of the 1st and 4th (or 2nd and 3rd) point positions was equal to the compound nuclei mass approximately. And the 3rd point was kept at ~132 constantly for different fission systems n+233 U, n+235U, n+233Pu.  相似文献   
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232Th 中子诱发裂变产额在Th/U 燃料循环的核能开发中具有重要的意义,在现有国际评价产额数据库基础上,结合最新的实验数据,对产物核的质量分布和反应堆计算所需的重点产物核进行了比对。这些产物核包括95Mo,99Tc,101Ru,103Rh,109Ag,133Cs,147Sm,149Sm,150Sm,151Sm,152Sm,143Nd,145Nd 和153Eu 等,对有分歧的133Cs,152Sm 和153Eu 累积产额数据进行了评价调整。最后推荐给出了n+232Th 裂变的产额数据库,作为CENDL 库的组成部分。The yields of n+232Th fission are important in study of the Th/U fuel cycle. Based upon the evaluated nuclear data libraries and recent experimental data,comparison and evaluation for yield mass distribution and cumulativeyield were performed for those products are needed and important in reactor calculations,including 95Mo,99Tc,101Ru,103Rh,109Ag,133Cs,147Sm,149Sm,150Sm,151Sm,152Sm,143Nd,145Nd adn 153Eu etc. Adjustments were made for 133Cs, 152Sm and 153En which have discrepancies among the libraries. Database for n+233Th fission yield is recommended as a part of CENDL update.  相似文献   
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Based on the neutron induced fission fragment mass distribution data up to  相似文献   
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