混合评价核数据库系统HENDL3.0研发及其在先进核能系统设计中应用
发布时间：2018-08-07 18:17
【摘要】：FDS团队结合聚变堆、先进裂变堆、聚变驱动次临界堆、加速器驱动次临界堆等核能系统对应用核数据的需求,设计开发出混合评价核数据库HENDL。HENDL包括输运核数据库、嬗变与活化核数据库、辐照损伤核数据库等,并针对先进核能系统的物理特点,从能量自屏效应、热散射效应、温度多普勒效应等方面进行了精确的截面修正。HENDL已通过国际基准模型与实验的验证与确认,并在ADSCLEAR、FDS-SFB为代表的重大核工程与核能研究中得到了广泛应用。
[Abstract]:The FDS team designed and developed a hybrid evaluation nuclear database (HENDL.HENDL), which includes transport nuclear data, in combination with nuclear power systems such as fusion reactor, advanced fission reactor, fusion driven subcritical reactor, accelerator driven sub-critical reactor, and so on. In view of the physical characteristics of advanced nuclear energy system, such as transmutation and activation nuclear database, radiation damage nuclear database, energy self-screen effect, heat scattering effect, The precise cross-section correction of temperature Doppler effect. HENDL has been verified and confirmed by the international benchmark model and experiment, and has been widely used in the important nuclear engineering and nuclear energy research represented by ADSCLEARFDS-SFB.
【作者单位】： 中国科学院核能安全技术研究所中子输运理论与辐射安全重点实验室;
【基金】：国家自然科学基金(11405204、11305205、10675123),国家自然科学基金(11405204、11305205、10675123) 中国科学院战略先导专项(XDA03040000),中国科学院信息化专项(XXH12504-1-09) 国家ITER 973计划(2014GB112001) 产业化基金
【分类号】：TL329;TP311.13
，
本文编号：2170918
[Abstract]:The FDS team designed and developed a hybrid evaluation nuclear database (HENDL.HENDL), which includes transport nuclear data, in combination with nuclear power systems such as fusion reactor, advanced fission reactor, fusion driven subcritical reactor, accelerator driven sub-critical reactor, and so on. In view of the physical characteristics of advanced nuclear energy system, such as transmutation and activation nuclear database, radiation damage nuclear database, energy self-screen effect, heat scattering effect, The precise cross-section correction of temperature Doppler effect. HENDL has been verified and confirmed by the international benchmark model and experiment, and has been widely used in the important nuclear engineering and nuclear energy research represented by ADSCLEARFDS-SFB.
【作者单位】： 中国科学院核能安全技术研究所中子输运理论与辐射安全重点实验室;
【基金】：国家自然科学基金(11405204、11305205、10675123),国家自然科学基金(11405204、11305205、10675123) 中国科学院战略先导专项(XDA03040000),中国科学院信息化专项(XXH12504-1-09) 国家ITER 973计划(2014GB112001) 产业化基金
【分类号】：TL329;TP311.13
，
本文编号：2170918
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