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1.
严小松  刘荣  鹿心鑫  蒋励  王玫  林菊芳 《物理学报》2012,61(10):102801-102801
为校验次临界能源堆的概念设计,建立了贫化铀/聚乙烯球壳交替系统, 采用活化法测量238U的中子俘获率. 贫化铀片置于系统内与入射D离子束成90o的方向上活化 ,用HPGe探测器测量238U俘获中子衰变产生的239Np 衰变产生的277.6 keV特征γ射线计数,实验修正了贫铀片对277.6 keV γ射线的自吸收, 得到了交替系统中238U (n, γ)反应率的径向分布,反应率的相对不确定度为3.5%-3.7%, 并计算得到系统上整个贫铀区中238U的总中子俘获率为2.24 ± 0.09. 用MCNP5程序在常用ENDF库下进行了模拟计算, 238U (n, γ)反应率分布计算与实验一般在5%以内符合, 总俘获率在1%以内符合.  相似文献   

2.
文章作者采用核活化法和核裂变法实验研究了加速器D-T中子、D-D中子以及~(252)Cf自发裂变中子在纯水泥体上的反射中子,获得了反射中子引起的6种高阈能活化箔的活化反应率以及~(235)U(包镉)和~(238)U裂变反应率.采用反冲质子法测量了4种厚度(4.5,9,18,27cm)聚乙烯板的角度中子谱.获得了聚乙烯铁铍组合壳体内距装置中心0,9.7,12.8和17.3cm 4个位置1MeV以上的中子能谱.采用铝核素标准截面相对测量法,获得了~(175)Lu、~(89)Y核素的(n,2n)反应截面.文章还分析了实验的不确定度.  相似文献   

3.
中子诱发裂变反应率是表征和检验中子在材料中的输运、裂变放能等过程的重要物理量.贫化铀球壳裂变反应率径向分布数据,可为铀核数据宏观检验及研究裂变放能与贫化铀球壳厚度的关系提供数据支持.本文设计了内径为13.1 cm,外径分别为18.10,19.40,23.35,25.40,28.45 cm的五种不同厚度的贫化铀球壳组合装置;利用位于球壳中心的氘氚中子源轰击贫化铀球壳装置,中子产额约为3×10~(10)—4×10~(10)s~(-1);在"赤道"平面与入射氘束成45°方向测量裂变反应率随径向分布的情况.为了克服裂变室和俘获探测器等自身对模型和中子场的扰动,本文选择与装置材料相同的贫化铀材料作为活化探测器,以活化探测器中的裂变碎片143Ce发射的γ射线作为测量对象,通过HPGe探测器测量的γ射线数,基于~(143)Ce裂变产额数据反推裂变反应率.通过实验获得了贫化铀球壳内的裂变率及其径向分布规律,裂变反应率和相对标准不确定度分别位于5.28×10~(-29)—7.58×10~(-28)之间和6%—11%之间.基于蒙特卡罗程序和ENDF/BVI.8数据库完成了模拟计算,并与实验结果进行了对比分析,两者在不确定度范围内一致.  相似文献   

4.
离线测量钍快中子裂变反应率方法   总被引:1,自引:0,他引:1       下载免费PDF全文
冯松  刘荣  鹿心鑫  羊奕伟  王玫  蒋励  秦建国 《物理学报》2014,63(16):162501-162501
钍快中子裂变反应率是钍铀燃料循环中的重要数据.为了测量基于聚变-裂变混合能源堆包层概念设计的钍样品在宏观中子学装置中的钍快中子裂变数据,发展了钍快中子裂变率的离线活化γ测量方法.通过测量232Th裂变碎片85mKr的β衰变产物85Rb发射的151.16 keV特征γ射线,并结合钍裂变产额数据,获得了钍样品装置中232Th裂变反应率的分布.详细介绍了此方法的原理和影响因素,并利用14 MeV的D-T中子源在贫铀球壳中开展了校验实验,实验不确定度为5.3%—5.5%.采用MCNP5程序和ENDF/B-VI及ENDF/B-VII数据库模拟计算的结果与实验结果在实验不确定度内基本符合,这证明该方法能够有效地模拟装置中232Th裂变反应率.  相似文献   

5.
准确定量铀氧化物样品中238U的含量对于裂变产额测量等工作具有重要意义,其定量方法的研究对于涉及238U的绝对测量的诸多实验都具有参考价值。利用四川大学2.5 MeV质子静电加速器产生的准单能中子对八氧化三铀样品进行中子活化,用高纯锗探测器测量活化产物的β衰变子体239Np的277.6 keV特征γ射线,利用已知的活化截面,算出样品中238U的质量占比为79.1%,不确定度为6.2%。利用电感耦合等离子体质谱法对样品中238U的含量进行了测量,其质量占比为59.2%。此外,基于EA3000元素分析仪、卡尔费休电位滴定仪和TGA-DSC2同步热分析质谱联用仪,测知样品中不含N元素,含水量在2.2%以下。并利用PIXE方法排除了样品中含有Al元素以上杂质,利用EPBS方法测知样品中U/O原子数比为1:3.6,误差约2%,推知样品中238U质量占比为80%,验证了活化法测得的238U含量。最终测得样品中238U的质量占比为79.1%,不确定度6.2%。对照按U3O8分子式折算的84.5%,考虑到水分含量等,此结果合理。The accurate quantification of 238U in uranium oxides is of great importance for measurements of fission yield. The study for the method of 238U quantification has significance to lots of experiments involving absolute measurement of 238U. The reaction (n, γ) in the triuranium octoxide samples was induced by T(p,n)3He quasi-monoenergetic neutrons provided by the 2.5 MeV proton electrostatic accelerator in Sichuan University. The 277.6 keV characteristic γ ray of 239Np that comes from β-decay of the activation product 239U was detected by a HPGe detector. With the known (n, γ) cross section, the mass percentage of 238U in samples was determined to be 79.1%, with the uncertainty of 6.2%. ICP-MS was also used in the quantification of 238U in samples, its result was 59.2%. Meanwhile, the samples were analyzed by other several methods and the results showed that less than 2.2% H2O, no nitrogen, and no other impurity elements above Al were contained in the samples. EPBS was used to measure the atomic ratio of U and O and it was found that the mass percentage of 238U in samples was about 80%, verifying the result 79.1% of INAA.  相似文献   

6.
钍俘获反应率离线伽马测量方法   总被引:1,自引:0,他引:1       下载免费PDF全文
羊奕伟  刘荣  严小松 《物理学报》2013,62(3):32801-032801
为了测定聚变-裂变反应堆模型钍包层中的钍俘获率以及钍-铀转化率, 探索了一种新的钍活化离线γ测量法. 利用测量232Th俘获反应产物233Th衰变链中233Pa衰变放出的311.98 keV 特征γ射线, 来反推计算并最终确定232Th(n,γ)233Th的反应率, 测试实验中不确定度约6% (233Th/232Th量级为10-17情况下). 详细介绍了此方法的背景和原理方法, 并进行简单的校验实验, 证明其能够较好地得到模拟装置中的俘获率. 与瞬发γ测量法以及质谱分析法进行对比, 本方法更适合用于聚变-裂变反应堆模型钍包层中的钍俘获率以及钍-铀转化率测量, 并有望进一步测量其他相关参数.  相似文献   

7.
铀同位素比(~(235)U/~(238)U)高精度测量在核能安全领域具有重要的研究意义和应用价值,本文基于高灵敏度可调谐吸收光谱技术,结合脉冲激光烧蚀产生等离子体的样品处理方式,实现了固体材料中~(235)U和~(238)U铀同位素比的高精度测量.实验测量选择l=394.4884 nm/394.4930 nm (vacuum)作为~(235)U/~(238)U分析线,详细研究了缓冲气体及其压力对激光烧蚀等离子体中铀原子存在时间的影响.结果表明氦气作为缓冲气体更有利于铀原子吸收光谱测量.实验获得了测量铀原子吸收光谱的最佳测量条件,并测量了~(235)U含量分别为4.95%, 4.10%, 3.00%, 1.10%和0.25%的五种样品,获得了~(235)U和~(238)U的高分辨率吸收光谱信号.不同含量样品吸收光谱测量与统计分析表明, ~(235)U吸收信号的线性度良好,拟合相关系数为0.989,检测限为0.033%(3s),吸收光谱测量重现性优于固定波长法.激光烧蚀结合可调谐吸收光谱技术适用于铀同位素比测量分析,在核燃料的同位素快速分析方面有很大的应用潜力.  相似文献   

8.
羊奕伟  刘荣  蒋励  鹿心鑫  王玫  严小松 《物理学报》2014,63(16):162801-162801
开展了钍样品装置内钍核参数的积分中子学基础研究.参考混合堆概念设计搭建了内部放置了钍样品的一维贫铀/聚乙烯交替系统装置,采用加速器D-T中子源模拟聚变堆芯,利用前期开发的离线伽马测量方法测定了不同位置、不同中子谱情况下的232Th(n,γ)反应率,不确定度约为5%.结果显示,聚乙烯对14.1 MeV中子的慢化作用可有效提升钍俘获率,且贫铀对钍俘获率也有显著提升作用.实验结果与主流核数据库计算结果的对比显示,ENDF/B-VI.6和JENDL-3.3数据库的计算值比实验值平均约大6%,而较新的ENDF/B-VII.0数据库的计算值比实验值平均约大4%.因此,相比于之前数据库的钍核数据,ENDF/B-VII.0的计算值与实验结果匹配得较好,可作为相关概念设计的推荐核数据库.  相似文献   

9.
对脉冲堆而言,在无强吸收介质时,堆外任何一点的中子谱可近似地由热中子谱、1/E谱和裂变谱叠加而成。根据这一原理,利用包镉的^235U转换靶和裸^235U转换靶在固体径迹探测器上产生的裂变径迹数差,确定热中子谱(镉下中子);用包镉的^235U转换靶和^238U转换靶在固体径迹探测器上产生的裂变径迹数差,获得1/E谱和裂变谱。  相似文献   

10.
等价电子耦合波函数的构造和矩阵元计算   总被引:1,自引:0,他引:1       下载免费PDF全文
李晓梅  陈健华 《物理学报》1999,48(9):1593-1600
按(U,D)L-LSQ-R耦合格式构造等价电子耦合波函数(这里U(D)是自旋向上(向下)电子的轨道角动量,Q是准旋,R是自旋-准旋交换算符),只需对半满壳层计算耦合波函数,其它电子数耦合波函数可通过准旋升、降算符和自旋-准旋交换算符的作用得到.对p,d,f,g壳层进行了耦合波函数和产生-湮没算符约化矩阵元计算.理论分析和实际计算表明,(U,D)L-LSQ-R耦合格式比一般LS耦合格式更便于计算. 关键词:  相似文献   

11.
Actinides have widely entered the environment as a result of nuclear accidents and atmospheric weapon testing. These radionuclides, especially uranium, are outstanding radioactive pollutants, due to their high radiotoxicity and long half-lives. In addition to this, since depleted uranium (DU) has been used in the Balkan conflict in 1999, there has been a concern about the possible consequences of its use for the people and environment. Therefore, accurate, precise and simple determination methods are necessary in order to evaluate the human dose and the concentration and effects of these nuclides in the environment. The principal isotopes of uranium e.g. 235U and 238U are of primordial origin and 234U present in radioactive equilibrium with 238U. 236U occurs in nature at ultra trace concentrations with a 236U: 238U atom ratio of 10−14. Concentrations of uranium in soil samples were determined using inductively coupled plasma mass spectrometry (ICP-MS) and isotope ratios of uranium were measured using a thermal ionisation mass spectrometer. Radioactive dis-equilibrium of 234/238U, depletion of 235/238U and significant evidence of 236U/238U were noticed in soil samples.   相似文献   

12.
The half-life of the 238U shape isomer and its yield ratio in a (γ, γ') reaction have been measured by pulsed beam techniques at a bremsstrahlung endpoint energy of 12 MeV. From the results (T12 = 146 ± 22 ns, Yiso/Ypr = (6.6 ± 1.0) × 10?6) the isomeric fission cross section has been deduced. Combining this information with the results of a previous 238U(γ, xnγ) study, an upper limit for the branching ratio Γγ/Γf|II < 13 for the decay of 238mU can be obtained. The decay properties of the 236U and 238U shape isomers are discussed.  相似文献   

13.
In order to check the conceptual design of the subcritical blanket in a fusion-fission hybrid reactor, a depleted uranium/polyethylene simulation device with alternate shells has been established. The measurement of the 238U(n, 2n) reaction rate was carried out using an activation technique, by measuring the 208 keVγ rays emitted from 237U. The self-absorption of depleted uranium foils with different thicknesses was experimentally corrected. The distribution of the 238U(n, 2n) reaction rate at 90° to the incident D+ beam was obtained, with uncertainty between 5.3% and 6.0%. The experiment was analyzed using MCNP5 code with the ENDF/BVI library, and the calculated results are all about 5% higher than the measured results.  相似文献   

14.
The reaction cross-sections of 238U (n, γ)239U have been experimentally determined at neutron energies of 6.117 ± 0.119 MeV, 4.626 ± 0.086 MeV, and 3.622 ± 0.348 MeV employing the relative activation approach along with the off-line γ-ray spectroscopy method. The D (d, n)3He reaction was utilized to obtain monoenergetic neutrons of the required energy, and the 197Au (n, γ)198Au reaction cross-sections were adopted as the referential standard to ascertain the neutron capture cross-sections of 238U. Furthermore, the effects of low-energy scattered neutrons, neutron fluence fluctuations, counting of geometric corrections when measuring γ-rays, and neutron and γ-ray self-absorption caused by the sample thickness have been considered and revised in the present work. For a comparison with experimental results, the cross-sections of the 238U (n, γ)239U reaction were calculated theoretically with the original parametric TALYS-1.9 program. The experimental measurements were in contrast to previous experimental results and the evaluation data available for ROSFOND-2010, CENDL-3.2 and ENDF/B-VIII.0.  相似文献   

15.
Bremsstrahlung induced photofission of 197Au and 238U has been measured for energies Emaxγ = 0.8 to 2.2 GeV using catcher foil techniques. The mass distributions of the fission fragments of uranium were measured as a function of the maximum bremsstrahlung energy. The peak-to-valley and forward-backward ratios have been determined for 238U.  相似文献   

16.
The electronic structure of U and Ge in the solid solutions U(Al1−x Gex)3 is investigated by measuring x-ray line shifts. It is shown that uranium has the mixed valence U3+ [Rn](5f 3)-U4+ [Rn](5f 2) over the entire composition range (0⩽x⩽1) and that the population of the uranium 5f shell increases by ∼0.28 5f electrons/U atom from UAl3 (x=0) to UGe3 (x=1). The electronic structure of Ge is close to the electronic structure of Ge metal over the entire composition range 0<x⩽1. No variation of the population of the Ge 4p shell is detected to within the experimental error (∼0.1 4p electrons/Ge atom) as the composition varies from x=0.2 to 1. It is established that the delocalization of a U 5f electron occurs as a result of its transition to the s or d band of the same uranium atom. Fiz. Tverd. Tela (St. Petersburg) 39, 1505–1508 (September 1997)  相似文献   

17.
Spallation neutrons produced in the collision of a 2.33GeV deuteron beam with a large lead target are moderated by a thick graphite block surrounding the target and used to activate the radioactive samples of natU and Th put at three different positions, identified as holes “a”, “b” and “c” in the graphite block. Rates of the (n, f), (n, $ \gamma$ and (n, 2n) reactions in the two samples are determined using the gamma spectrometry. The ratios of the experimental reaction rates, R (n, 2n)/R (n, f), for 232Th and natU are estimated in order to understand the role of the (n, x n) kind of reactions in Accelerator-Driven Sub-critical Systems. For the Th-sample, the ratio is ~ 54 (10)% in the case of hole “a” and ~ 95 (57)% in the case of hole “b” compared to 1.73(20)% for hole “a” and 0.710(9)% for hole “b” in the case of the natU sample. Also the ratio of fission rates in uranium to thorium, natU (n, f)/ 232Th (n, f), is ~ 11.2 (17) in the case of hole “a” and 26.8(85) in hole “b”. Similarly, the ratio 238U (n, 2n)/ 232Th (n, 2n) is 0.36(4) for hole “a” and 0.20(10) for hole “b” showing that 232Th is more prone to the (n, x n) reaction than 238U . All the experimental reaction rates are compared with the simulated ones by generating neutron fluxes at the three holes from MCNPX 2.6c and making use of the LA150 library of cross-sections. The experimental and calculated reaction rates of all the three reactions are in reasonably good agreement. The transmutation power, P norm as well as P norm/P beam of the set-up is estimated using the reaction rates of the (n, $ \gamma$ and (n, 2n) reactions for both the samples in the three holes and compared with some of the results of the “Energy plus Transmutation” set-up and TARC experiment.  相似文献   

18.
The fission decay of highly neutron-rich uranium isotopes is investigated which shows interesting new features in the barrier properties and neutron emission characteristics in the fission process. 233U and 235U are the nuclei in the actinide region in the beta stability valley which are thermally fissile and have been mainly used in reactors for power generation. The possibility of occurrence of thermally fissile members in the chain of neutron-rich uranium isotopes is examined here. The neutron number N = 162 or 164 has been predicted to be magic in numerous theoretical studies carried out over the years. The series of uranium isotopes around it with N = 154–172 are identified to be thermally fissile on the basis of the fission barrier and neutron separation energy systematics; a manifestation of the close shell nature of N = 162 (or 164). We consider here the thermal neutron fission of a typical representative 249U nucleus in the highly neutron-rich region. Semiempirical study of fission barrier height and width shows that 250U nucleus is stable against spontaneous fission due to increase in barrier width arising out of excess neutrons. On the basis of the calculation of the probability of fragment mass yields and the microscopic study in relativistic mean field theory, this nucleus is shown to undergo exotic decay mode of thermal neutron fission (multi-fragmentation fission) whereby a number of prompt scission neutrons are expected to be simultaneously released along with the two heavy fission fragments. Such properties will have important implications in stellar evolution involving r-process nucleosynthesis.   相似文献   

19.
Two-step photoionization of an atomic beam and quadrupole mass analysis have been used for the precise measurement of the isotope shift between uranium isotopes 235 and 238 and the hyperfine structure of 235U. For the 5915 Å ground-state transition 15 hfs components were found. The residual atomic beam was isotopically enriched by factors 2.5 and 10 for 235U and 238U, respectively.  相似文献   

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