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。     

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     

裂变靶探测系统中子灵敏度的理论计算

采用文献提供的裂变碎片在Si-PIN探测器中的平均能量沉积公式及修正系数,构建了狭缝外延式高灵敏裂变中子探测系统中子灵敏度的理论计算模型,通过Fortran程序进行了相关的理论模拟与数值计算.并与实测的中子灵敏度进行了比较.     

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.     

Neutron Nuclear Data Evaluation of Cesium Isotopes for JENDL-4.0

For the development of JENDL-4.0, neutron nuclear data for fission product nuclides, ^{133,134,135,136,137}Cs, were revised in the incident neutron energy range from 1 eV to 20MeV by using a coupled-channels optical model (OM), and nuclear reaction models. The OM potential parameters were determined for stable ¹³³Cs to reproduce the experimental data of total and elastic scattering cross sections and angular distributions of elastically scattered neutrons. The present results reasonably reproduce measured data for (n; 2n), (n; p), (n; α), and capture reactions on ¹³³Cs. Important differences between the present results and JENDL-3.3 are found for the capture cross sections of ^134,137Cs. The cross section obtained for ¹³⁷Cs was smaller than that in JENDL-3.3. This result makes the transmutation of medium-lived ¹³⁷Cs increasingly difficult. The production probabilities of metastable states for ^134,138Cs via capture reactions on ^133,137Cs are compared with experimental values. The present result for ^134m Cs production is marginally consistent with measured data. However, a large discrepancy is recognized for ^138m Cs production. The γ-ray emission data were evaluated with available measurements, and newly compiled in JENDL-4.0. Maxwellian-averaged capture cross sections were calculated in the energy range from 1 to 103 keV, and are compared with other derived data.     

Evaluation of Neutron Nuclear Data for Sodium-23

Neutron nuclear data of ²³Na have been evaluated in the neutron energy region up to 20 MeV. Evaluated are the elastic and inelastic scattering, capture, (n, 2n), (n, p), (n, α), (n, np), (n, nα) reaction and γ-ray production cross sections, and the angular and energy distributions of neutrons and γ-rays. The evaluation is mainly based on nuclear model calculations. The pre-equilibrium and direct-reaction processes were taken into account in addition to the compound process. The evaluated data have been compiled into the latest version of JENDL, JENDL-3.3.     

Evaluation of Neutron Nuclear Data on Bromine and Krypton Isotopes for JENDL-4.0

Neutron nuclear data on ^79,81Br and ^{78,80,82,83,84,85,86}Kr have been evaluated for the evaluated nuclear data library JENDL-4.0 in the energy region from 10^?5 eV to 20 MeV. The resolved resonance parameters were adjusted so as to reproduce recommended or measured thermal capture cross sections for some isotopes. The statistical model was applied to calculate the cross sections above the resolved resonance region. In the calculations, coupled-channel optical model parameters were used for neutrons. Preequilibrium and direct-reaction processes were taken into account in addition to the compound process. The present evaluation is consistent with available experimental data. The evaluated results were compiled into JENDL-4.0.     

Evaluation of Neutron Nuclear Data for Z>88 Minor Nuclides

Neutron nuclear data for 15 minor nuclides (Z>88) have been evaluated in the energy range of 10^?5 eV–20 MeV. Since only few experimental data are available, the present evaluation was mainly based on the systematics of the data from neighboring nuclides and also optical and statistical model calculations. The evaluations have been carried out for neutron cross sections of total, elastic scattering, inelastic scattering, (n, 2n), (n, 3n), (n, 4n), fission and capture reactions. In addition, angular and energy distributions of the emitted neutrons and average number of the emitted neutrons per fission were also evaluated. The results were compiled in the ENDF/B-V format and stored in the JENDL-3.     

Evaluation of Neutron Nuclear Data for Mercury

Neutron nuclear data of stable mercury isotopes (¹⁹⁶Hg, ¹⁹⁸Hg, ¹⁹⁹Hg, ²⁰⁰Hg, ²⁰¹Hg, ²⁰²Hg and ²⁰⁴Hg) have been evaluated in the energy range of 10^?5eV–20MeV. Evaluated quantities are the total, elastic and inelastic scattering, capture, (n, 2n), (n, 3n), (n, p), (n, d), (n, α), (n, np), (n, nα) reaction and γ-ray production cross sections, the resonance parameters, and the angular and energy distributions of emitted neutrons and γ-rays. The evaluation is mainly based on nuclear reaction model calculations. Statistical-model calculation played a significant role in the determination of the reaction cross sections. The evaluated data have been compiled in the ENDF-6 format, and are used for the design study of a mercury target system proposed at the Neutron Science Research Center, Japan Atomic Energy Research Institute.     

235U快中子核反应截面协方差评价

本文基于最小二乘不确定度传递方法,建立²³⁵U中子裂变核反应截面模型依赖型与非模型依赖型协方差评价体系。通过针对实验测量较丰富的中子反应总截面、辐射俘获、(n,2n)等核反应实验数据不确定度源项分析,为协方差评价提供实验基础,并给出对应核反应截面的非模型依赖型协方差评价数据。通过开展快中子能区²³⁵U核反应理论模型参数灵敏度计算与分析,导出实验测量缺乏的核反应截面模型依赖型协方差评价数据。经上述系统评价,所得协方差数据与核反应截面中心值研究过程自洽、物理合理,并按国际标准ENDF-6格式输出,便于核工程用户使用。     

Evaluation of Neutron Nuclear Data for Uranium-233

Neutron nuclear data of ²³³U have been evaluated in the energy range from 10-⁵ eV to 20 MeV. Evaluated quantities are the total, fission, capture, elastic and inelastic scattering, (n,2n) and (n,3n) reaction cross sections, and the average numbers of prompt and delayed neutrons emitted per fission. The thermal and resonance cross sections have been evaluated on the basis of the measured data. The resolved resonance parameters are given up to 100 eV and the unresolved resonance parameters between 100 eV and 30keV. The total and fission cross sections have been evaluated in the higher energy region on the basis of the recently measured data, while the theoretical calculation with the optical, statistical and evaporation models has been used for evaluation of the other cross sections. The presently adopted optical potential parameters have reproduced well the experimental total cross section in the entire energy range as well as the measured data of the s-wave strength function. The structure observed in the vp values below 1 MeV is reproduced by the semi-empirical formula based on the fission fragment kinematics. The presently evaluated fission cross section is considerably lower than that of ENDF/B-IV between 10 and 50keV. This low fission cross section is expected to resolve the ^Keff discrepancy pointed out from the benchmark tests in ²³³U critical assemblies.