天然汞的全套中子数据评价

在１０￣（－５）＿ｅＶ－２０ＭｅＶ中子能量范围内对天然汞的中子核数据进行评价。评价内容包括总的、弹性、去弹、总非弹、３０条分立能级、连续非弹、（ｎ，２ｎ）、（ｎ，３ｎ，）、（ｎ，ｎ＇Ｐ）、（ｎ，ｎ＇α）、（ｎ，Ｐ）、（ｎ，α）、（ｎ，ｄ）、（ｎ，ｔ）和（ｎ，γ）截面；次级中子角分布；双微分截面（ＤＤＣＳ）；γ射线产生数据等。评价根据有效实验数据（至１９９３年）和ＵＮＦ－９２￣［１］理论计算。评价数据以ＥＮＤＦ／Ｂ６格式录入中国评价核数据库ＣＥＮＤＬ－２．１版（ＭＡＴ＝１８００），并提供核工程有关部门使用。     

天然铊的全套中子数据评价

天然铊的中子核数据评价在１０￣（－５）ｅＶ－２０ＭｅＶ中子能量范围内进行，它的内容包括总的、弹性、去弹、总非弹、１６条分立能级、连续非弹、（ｎ，ｐ）、（ｎ，ａ）（ｎ，ｄ）、（ｎ，ｔ）、（ｎ，２ｎ）、（ｎ，３ｎ）、（ｎ，ｎ＇ｐ）、（ｎ，ｎ＇ａ）和（ｎ，ｒ）反应截面；次级中子角分布；双微分截面（ＤＤＣＳ）；ｒ射线产生数据以及共振参数等。评价以到１９９３年为止的有效实验数据和理论计算（ＵＮＦ－９２程序）为依据。评价数据以ＥＮＤＦ／Ｂ６格式给出并收入中国评价核数据库（ＣＥＮＤＬ－２．１）版（ＭＡＴ＝１８００）和提供核工程有关部门使用。     

裂变元素中子共振反应的裂变和俘获截面的相关分析

我们曾用多能级展开的Adler-Adler公式对裂变元素的中子共振反应(裂变或俘获)截面作过分析,求出裂变或俘获截面的共振参数。本工作是进一步对同一核素的裂变和俘获截面两组实验数据作相关分析,以求取同一核素两种截面相应的共振参数。     

中子核数据评价现状和发展

评述了国际、国内核数据评价的现状和发展，对我国核数据评价的发展提出了看法。     

~(236)Np全套中子数据更新评价

裂变核全套中子评价数据为反应堆设计和安全运行、核燃料循环、估算高燃耗反应堆中次锕系核素的产生量及嬗变研究等提供重要的基础数据。本文基于全新的238Np中子光学模型势参数,对n+236Np核反应进行理论分析,并根据Np各同位素反应截面系统变化规律,对模型参数进行了调整,最后完成了全套中子数据的更新评价,与CENDL-3.1评价结果相比有较明显的改进。     

~(238)Np全套中子数据更新评价

裂变核全套中子评价数据为反应堆设计和安全运行、乏燃料次锕系核素嬗变、嬗变系统及高燃耗反应堆设计提供重要的基础数据。本文以一套全新的n+238 Np的中子光学模型势参数为基础进行理论分析,并根据Np各同位素反应截面系统变化规律,对模型势参数进行了调整,最后完成了全套中子数据的更新评价,与CENDL-3.1评价结果相比有较明显的改进。     

中子入射砷核同位素反应全套微观数据的计算与分析

基于光学模型假设和中子与天然砷反应的总截面、去弹截面以及弹性散射角分布的实验数据,获得了一组0.1~20 MeV能量区域内普适于中子与砷核同位素反应的光学势参数。并以该组光学模型参数为前提,利用以光学模型、扭曲波Born近似理论、统一的Hauser-Feshbach统计理论和激子模型等理论为核心的UNF程序,计算了中子与As及其同位素的反应截面、能谱和双微分截面值,并对理论计算值和实验数据进行了比较和分析,理论计算结果与实验数据符合较好,同时给出了无实验数据的区域的理论结果。     

快堆伪裂变产物数据的计算

从微观评价核数据库出发 ,计算给出了快堆谱的伪裂变产物数据 ,包括一群的截面数据和多群的全套中子数据 ,裂变核有2 3 5U和2 3 9Pu。截面数据有全截面、弹性散射、非弹散射、(n ,γ)、(n ,2n)截面 ,多群全套中子数据还包括次级中子角分布和能谱。数据以ENDF B -6格式给出 ,同时还分析讨论了数据误差和可靠性 ,数据可用于实际的快堆计算     

New Evaluation of Neutron Nuclear Data for Zinc Isotopes

New evaluation of neutron-induced nuclear data for five stable isotopes of zinc (mass numbers A = 64, 66, 67, 68, and 70) was consistently carried out in the incident neutron energy range from 10^?5 eV up to 20MeV. In the low energy region up to about 100keV, the resonance parameters were evaluated by taking account of the available measured data. In the fast neutron region, the comprehensive calculations with nuclear reaction models, in which compound, preequilibrium, and direct processes are taken into account, were performed to estimate cross sections for various reactions and double differential cross sections of emitted neutrons and γ-rays. The comparisons of the evaluated cross sections with the experimental data and existing evaluated nuclear data libraries are made and show a good agreement with the measurements.     

Evaluation of neutron nuclear data of praseodymium-141 and -143

For the next version of JENDL general purpose file, neutron nuclear data on ^141,143Pr are evaluated considering cross sections and spectra provided from experiments in the fast neutron energy region up to 20 MeV. Total and elastic cross sections are derived from optical model. Pre-equilibrium and direct-reaction processes are taken into account in addition to the compound process. The statistical model is applied to calculate the cross sections above the resolved resonance region. For unstable ¹⁴³Pr nuclide having less experimental data, we use the same parameters as ¹⁴¹Pr for mass-dependent and -independent terms in the optical potential. The resolved resonance parameter remains unchanged from JENDL-4.0. The present evaluations give consistent results with experimental data, reflecting newly measured one. The evaluated data are compiled in ENDF-6 format for the next version of JENDL.     

A function to provide neutron spectrum produced from the 9Be + p reaction with protons of energy below 12 MeV

A function to give the total neutron production cross section, angular distribution, and energy spectrum via the ⁹Be + p reaction has been created by fitting experimental data to characterize compact neutron sources with thick Be targets bombarded by protons with energy below 12 MeV. To examine the suitability of the function, calculations of the angle-dependent neutron energy spectra produced in thick Be targets with 4- and 12-MeV protons using the function were compared with corresponding experiments and calculations using the nuclear data libraries of ENDF/B-VII.0 and JENDL4.0/HE. The function was in better agreement with the experiments than the calculations using the libraries except for at backward angles. The ¹¹⁵In(n,n’)^115mIn reaction rates calculated using GEANT4 with source neutrons given by both the function and ENDF/B-VII.0 were compared with that measured at the RIKEN Accelerator-Driven Compact Neutron Source to evaluate the neutron spectrum above 1 MeV. The function slightly overestimated the measurement by 14% and the calculation with ENDF/B-VII.0 underestimated by 35%. It was concluded that the function can be applied in compact neutron source designs.     

核数据处理程序NECP-Atlas的开发与验证

本文开发了自主化的核数据处理程序NECP-Atlas,该程序将不同的核数据处理功能封装为不同的程序模块,可将评价核数据经过共振重构及线性化、多普勒展宽计算、不可分辨共振区处理、热中子散射计算、多群截面计算等过程,处理为WIMS-D/E格式多群数据库。采用WLUP（WIMSD library update project）基准题、国际临界安全基准题ICSBEP（international criticality safety benchmark evaluation project）等对NECP-Atlas加工产生的核数据进行验证,结果显示NECP-Atlas和NJOY-2016程序精度相当。