MENDF—一个计算200 MeV以下裂变核数据的程序(英文)

基于球型光学模型、 预平衡发射和Hauser-Feshbach统计等理论, 编制了MENDF（Medium Energy Nuclear Data for Fission）程序, 该程序适用于裂变核在入射粒子能量低于200 MeV的中低能区的全套核数据计算。 对于中子和质子在200 MeV以下诱发的核反应, 其全截面、 反应截面、 弹性散射微分截面、 裂变截面和裂变中子谱、 5种发射粒子的单举截面和相应的能谱等理论计算值与相应的实验值基本符合。 MENDF在我国已被广泛用于核数据计算及建立中能核数据库。Based on the spherical optical model, pre equilibrium and Hauser Feshbach statistical theory, the code MENDF (Medium Energy Nuclear Data for Fission) is written to calculate a complete set of nuclear data for fission nuclei in the medium low energy region (≤200 MeV). For neutron and proton induced reactions below 200 MeV, the total cross sections, reaction cross sections, elastic scattering differential cross sections, fission cross section, energy spectra of fission neutron and five kinds of emitting particles, etc. are calculated by MENDF. The calculated data generally agree with their corresponding experimental data. MENDF is widely used for nuclear data calculation and to establish ENDF 6 formatted files for the medium low energy region in China.     

原子核密度经验公式与轻子-核DIS过程的核效应

在核密度模型基础之上利用原子核密度经验公式得到的核密度和利用电磁半径平方平均值得到的核密度分别计算了轻子 核深度非弹性散射过程中的核效应函数RHe/D(x, Q2), RLi/D(x, Q2), RC/Li(x, Q2), RCa/Li(x, Q2), 发现利用由原子核密度经验公式得到的核密度计算核效应函数所得结果与NMC实验数据符合得较好, 并且优于用后者方法计算核效应函数的理论结果, 从而说明利用原子核密度经验公式研究核子结构函数核效应的合理性。 The nuclear effect functions in l A DIS process RHe/D(x, Q2), RLi/D(x, Q2), RC/Li(x, Q2) and RCa/Li(x, Q2) are calculated on the basis of the nuclear density model by using nuclear densities obtained from an empirical formula or the experimental values of the electromagnetic mean of radius square 〈r2〉, respectively．It is shown that the nuclear effect functions obtained from the empirical formula are in good agreement with the NMC experimental data, and better than the later ones．The empirical formula of the nuclear density can be used to study the nuclear effect of nucleon structure functions reasonably.     

评价核结构数据库的程序系统及其相关数据库

简要介绍了评价核结构数据库的程序系统,内容包括主要程序功能及其数据库 . The program system of evaluating nuclear structure data file and the relevant database are briefly introduced. The main functions of these program system and their derived database are also presented.     

爆发性核合成与核结构

讨论了天体物理环境中爆发性核合成及其与核结构的紧密关系.用反射不对称壳模型计算了远离稳定线丰中子核148Ba的低能八极转动带,结果与实验很好符合.展示了其应用于不稳定核低能态计算的有效性 ,以及在核天体物理研究中的应用前景.The explosive nucleosynthesis in the astrophysical environment and its close link to nuclear structure are discussed. The low lying octupole bands for neutron rich nucleus 148 Ba far from the stability line have been calculated by the reflection asymmetric shell model and the results are in good agreement with the experimental data, presenting the capability of the model for calculations of the low lying states of unstable nuclei as well as the foreground of application in nuclear astrophysics.     

核数据共享研究

科学数据共享的重要性已经引起了我国政府的重视,介绍了中国核数据中心在核数据共享项目进行的研究工作.该研究工作主要包括建立核数据数据库和共享平台的建设两方面的内容.The importance of scientific data sharing has been attracted attention of our government. The research of nuclear data sharing in China Nuclear Data Center are introduced. The work includes research of nucler database and development of online service system.     

238U(n,f)短寿命产物核累积产额的评价(英文)

为满足堆内或核爆中链式反应过程的燃耗值的计算需要，对裂变谱中子和14MeV中子诱发238U裂变的短寿命产物核的累积产额进行了评价。评价利用了所有可利用的实验数据， 经物理分析后， 使用AVERAGE程序加权平均， 用ZOTT程序进行同时评价， 给出了所要求能点的唯一最佳推荐数据， 并将评价结果与ENDF/B-VII， JEF-2.2， JENDL-3.2和CENDL-2的推荐数据进行了比较。 评价结果将用于CENDL-2的更新与升级。For reliable and consistent nuclear calculation, the cumulative yields for short lived fission products are evaluated based on the available experimental data for 238U fission induced by fission spectrum neutrons and ~14 MeV neutrons. The data are processed using codes AVERAGE for weighed average and ZOOT for simultaneous evaluation. The evaluated data are compared with those in the major international nuclear data libraries, including ENDF/B-VII, JEF-2.2, JENDL-3.2 and CENDL-2. The present evaluation will be used to improve and update the CENDL-2 library.     

温度相关核截面数据库在MCNP计算中的必要性研究

MCNP程序由于其几何模拟和核数据上的优越性,现在在反应堆的研究分析中已经得到较多应用。通过基准题的计算,定量地说明MCNP通过其自带的常温（294K）下的核素截面数据库不能够对反应堆进行非常准确的计算（由于反应堆内各种材料／位置的温度不同）,而且,它也不能够计算反应堆中与温度相关的量,如反应性温度系数。选用了一个带有不同温度下核素截面数据的MCNP输入格式的数据库,使用MCNP-4C对基准题进行了计算,发现计算结果与基准值符合得非常好。这说明通过使用不同温度下的核素截面数据库,MCNP可以准确计算温度系数和增殖系数等,从而说明在反应堆设计计算中制作不同温度下的核素截面库的必要性。Due to the advantage of geometry simulation and nuclear data, the code MCNP is now widely used in the reactor analysis. Based on our calculation of the fuel temperature reactivity coefficient benchmark, it is quantificationally proved that MCNP with its own cross section library can＇ t be used to simulate the reactor accurately and to calculate the temperature reactivity coefficient. Furthermore, we use MCNP- 4C with a database that contains temperature dependent nuclear cross sections to calculate the benchmark. The results are well agreement with benchmark results. This means that, with the temperature dependent nuclear cross sections library, MCNP can calculate the temperature reactivity coefficient and reactor multiplication factor accurately. So the temperature dependent nuclear cross section library should be processed to meet the requirement of reactor calculation.     

评价核结构数据库

本文简要介绍了评价核结构数据库(ENSDF)的组织结构、核数据的内容和应用范围、数据的及时更新和为各国用户的优良服务。 This paper introduces the following fields of Evaluated Nuclear Structure Data File,which are file organization and structure, evaluated data contents, application fields and in-timeupdate, and good services to world-wide users.     

核电池材料及核电池的应用

核电池具有体积小、寿命长、不受外界环境影响等优点,因而在航空航天、深海、极地、心脏起搏器、微型电机等领域得到广泛地应用。核电池的发展与所用材料的发展互相促进。从同位素放射源、电能转换、密封保护的角度介绍了核电池所用材料的发展和最新研究进展,同时也介绍了核电池现有和潜在的应用领域。Nuclear battery has lots of advantages such as small volume, longevity, environal stability and so on, therefore, it was widely used in aerospace, deep-sea , polar region, heart pacemaker, micro-electromotor and other fields etc. The application of nuclear battery and the development of its materials promote each other. In this paper the development and the latest research progress of nuclear battery materials has been introduced from the view of radioisotope, electric energy conversion and encapsulation. And the current and potential applications of the nuclear battery are also summarized.     

核碎裂在离子与生物分子相互作用中的效应

讨论了重离子辐照生物中核碎裂效应,给出与此相关的核碎裂研究现状和进展。The effect of nuclear fragmentation discussed. The status and perspectives of this data. in the topic interactions of heavy ions with biological are presented based On calculations and molecules is experimental.     

加速器驱动反应堆的靶实验及核废料嬗变与焚化

对加速器辅助驱动次临界核反应堆的最近研究进展,特别是靶实验结果,进行了评述 .通过对靶实验首次全产物截面的测定,达到了剥离反应与裂变反应二者产物的完全识别. The recent progresses in accelerator driven nuclear subcritical nuclear reactor, especially in target experimental data have been reviewed.The data contained all the isotopes producing cross sections. The reaction products were identified whether they came from the spallation or fission reaction .     

核爆发电问题中核燃料循环的中子学研究

研究核爆聚变电站中的一类中子学问题——如何利用核爆炸产生的大量中子生产核燃料.首先,根据核爆中子场的特点,确定可以利用的中子能量范围.用慢化理论对慢化材料的厚度进行估计,并用MCNP程序进行数值计算.研究如何利用中子反照效应减少造材料层的厚度,最后提出一个较合理的造材料技术路线.     

加速器驱动的核电站──干净现实的核能源

由一台１６００ＭｅＶ的强流质子加速器来辅助驱动一座熔盐核反应堆,从而组建一座新型的核电站．这座电站中裂变核燃料“燃烧”完全,没有长寿命的重锕系与裂片的核废料输出;并可以直接用天然存在的大量钍和贫铀元素作为核燃料来使用．核电站将２０％电能供给加速器运转,８０％电能并入电网．同时电站还可输出十分稀有的稳定同位素和短寿命医用同位素,作为副产品供应市场．这一干净的核能源就是加速器驱动式核反应堆．简称驱动堆;它没有核废料,比自持式核反应堆安全． A new type of nuclear power station can be built by a moltensalt reactor auxiliary driven by a strong neutron source produced by a intensive proton beam with the energy of 1600 MeV from a powerful accelerator. In the power station the nuclear fuels are completely burnt without some long-lived radioactive wastes both of heaVy actinide and fission products. Furthermore the thorium and sub-critical uranium which are massive existence in nature can be used as an available nuclear fuel in...     

通过惰性气体氙判断核试验信息的方法

全面禁止核试验条约的达成是防止核武器扩散的重要手段. 如何判断一次核试验的发生是一个关键课题. 研究了基于测量惰性气体氙同位素^133mXe,¹³³Xe,¹³⁵Xe和^131mXe来鉴别核试验和民用反应堆泄漏的方法. 通过分析这些处于复杂衰变链上核素的数量随时间的变化,寻找核试验与反应堆泄露事件的区别. 对两次朝鲜可疑的事件进行了测量和分析. 为了验证理论计算结果,设计了一次热中子辐照钚的模拟实验. 关键词： 全面禁止核试验条约核查 气体裂变产物 核试验判据 惰性气体氙核素     

TMSR白光中子源关键核数据实验进展

钍铀燃料循环核数据的精度和可靠性直接关系着钍基熔盐堆的安全性和经济性。目前大多数核数据都是基于铀钚燃料循环进行开发，若直接用在钍基熔盐堆上将会出现核设计不确定度较高的问题。为了提高钍基熔盐堆物理设计所需核数据的适用性，中国科学院上海应用物理研究所自行设计并建造了紧凑型的15 MeV电子加速器驱动的白光中子源(Photoneutron Source，PNS)，用于开展钍铀燃料循环核数据的实验测量。该装置已通过技术验收，并进行了一系列关键核素的核数据测量，检验了现用核数据的可靠性，为相关核素的核数据评价与改进提供了基础实验数据。     

Neutron multiplicity in the fission of 238U and 235U with neutrons up to 200 MeV

Prompt-fission-neutron multiplicities were measured for 238U(n,f) and 235U(n,f) from 0.4 to 200 MeV. The data are of great importance in connection with accelerator-coupled nuclear reactor systems incinerating actinides. We report that fission induced by 200 MeV neutrons produces approximately 10 more prompt neutrons than fission induced by reactor neutrons. Most neutrons are evaporated from the fission fragments and the prefission compound nucleus, as the preequilibrium emission of energetic neutrons accounts for a maximum of 15% of the prompt neutrons at 200 MeV.     

Transmutation of radioactive nuclear waste — present status and requirement for the problem-oriented nuclear data base

Transmutation of long-lived actinides and fission products becomes an important issue of the overall nuclear fuel cycle assessment, both for existing and future reactor systems. Reliable nuclear data are required for analysis of associated neutronics. The present paper gives a review of the status of nuclear data analysis focusing on the waste transmutation problem.