电感耦合等离子体质谱法测定环境样品中超痕量239Pu的238UH+谱线干扰研究

环境样品中239 Pu的含量非常低,即使经过基体放化分离,238 UH+复合离子对239 Pu的干扰仍然很严重,直接扣除干扰谱线信号对分析结果的准确度影响较大。从仪器物理测量的角度研究了降低238 UH+复合离子产率的方法,包括进样系统、激发系统和离子界面层。研究结果表明,膜去溶装置可降低238 UH+复合离子产率一个数量级以上。射频功率对238 UH+复合离子的产率有一定的影响。在雾化气流速最佳的条件下,238 UH+复合离子产率达到最小值。Xs锥测量238 UH+复合离子产率的结果相对采用Xt锥的测量结果略低一些。     

植物样品中低水平铀同位素分析

建立了一种植物样品中痕量铀同位素(~(238)U、~(235)U和~(234)U)的分析方法。通过高温灰化去除植物样品中有机质,采用混合酸消解样品灰分,应用UTEVA萃取色谱分离和纯化铀。化学分离过程中铀的回收率达94%,对Na、K、Ca等基体和干扰元素的去除率超过99%。用高灵敏度ICP-MS/MS同时测定了3种天然铀同位素含量,对~(238)U、~(235)U、~(234)U的检出限分别为3.05、0.34和0.04 pg/g,其中对~(238)U和~(235)U的检出限比文献报道值低1个数量级。对小麦粉标准参考物质中~(238)U的分析结果与参考值吻合,表明本分析方法可靠。将本方法应用于中国西安地区植物样品中铀同位素的分析,结果表明,该地区植物中铀含量和铀同位素比值处于天然水平,未发现人为铀污染。这是中国植物样品中3种天然铀同位素水平的首次调查。     

电感耦合等离子体质谱法分析小鼠组织中以及和DNA结合的贫铀浓度与235U/238U

在DU染毒动物模型基础上,采用ICP-MS技术同时测定各组织中铀浓度和235U/238U比值,分析DU在体内的分布和代谢规律;提取纯化肝肾组织中的基因组DNA,ICP-MS检测与DNA结合的DU浓度和235U/238U。以Pt为内标元素,补偿基体效应,组织中铀的检出限为0.0019～0.0981μg/kg;精密度(RSD)为0.92%～2.13%,回收率在100%±10%内。ICP-MS对贫铀气溶胶中235U/238U检测结果与经典的α谱仪检测结果相吻合。DNA样品采用中性溶液稀释,DNA中铀元素检出限为0.0016μg/kg DNA,回收率为98.3%±7.3%。样本测定结果显示,肾脏和骨骼对贫铀的蓄积能力最强,脑组织几乎不受贫铀影响,其它组织的DU蓄积能力介于二者之间。在肾、肝组织中,DU可以与DNA发生结合,与肾DNA结合更持久。组织中235U/238U随染毒铀同位素组成和浓度发生规律性改变。铀浓度与235U/238U均可以作为衡量核素污染类型和程度的敏感指标。     

萃取色层分离同位素稀释ICP-MS测定空气中费克 量钚

ICP-MS测定环境样品中超痕量^2^3^9Pu时,^2^3^8UH^+会对m/z239的测量带来干扰。测得UH^+的产生几率为4.6×10^-^5,通过三正辛胺色层分离后,对铀的去除率为10^4,可以有效地去除^2^3^8UH^+离子峰对^2^3^9Pu测定的干扰。钚的回收率为75%。同位素稀释法对^2^3^9Pu的检出限为4.5×10^-^1^5g/mL,方法的定量测定限为16×10^-^1^5g/mL。用所建立的方法测得我国某地区空气中^2^3^9Pu的浓度为4.8×10^-^1^7g/m^3。     

逆流色谱分离感应耦合等离子质谱在线测量超痕量钚

将逆流色谱（CCC）与感应耦合等离子质谱（ICP-MS）相联,研究了几种两相体系在CCC中的固定相保留率,从中选择1％TNOA-正庚烷作固定相,通过CCC富集分离钚并去除基体及干扰元素,通过研究在线分离条件及定量方法等,建成了CCC分离ICP—MS在线测量超痕量钚的方法。采用该方法分析得到实际土壤样品中^239Pu的含量与由传统的分离方法给出的结果相吻合。     

激光剥蚀-多接收电感耦合等离子体质谱法 测定含钚颗粒物中240 Pu/239 Pu比值

为高精度、准确地获取含钚颗粒物中具有核保障监督意义和核取证价值的钚同位素比值,建立了激光剥蚀-多接收电感耦合等离子体质谱(LA-MC-ICP-MS)测定含钚颗粒物中240 Pu/239 Pu的分析方法.采用检漏、安装排风罩和擦拭剥蚀池内壁等方式有效降低激光剥蚀产物沾污实验室和危及人身安全的潜在风险.联用扫描电迁移率粒径谱仪(SMPS)与激光剥蚀-多接收器等离子体质谱(LA-MC-ICP-MS)研究了激光剥蚀玻璃基体标样产生气溶胶的分布特性,结果表明,剥蚀产物的主要粒径是40~500 nm,应尽量采用水平管道连接激光剥蚀进样系统与MC-ICP-MS,含钚颗粒物分析后剥蚀池持续吹扫时间应大于15 min.采用外标归一化法离线校正质量分馏效应和离子计数器检测效率,建立了含钚颗粒物中240 Pu/239 Pu的LA-MC-ICP-MS分析方法,固定束斑直径30μm、脉冲重复率5 Hz、剥蚀时间5 s,调节能量密度使含钚颗粒物模拟样品中239 Pu的信号强度分别达2×104 cps和2×105 cps,本方法对240 Pu/239 Pu测量的相对实验标准不确定度小于1.4%(n=6),测量结果与参考值的相对偏差小于4.7%,仪器调试时间和单个样品测量时间分别为9.0和0.5 h.含钚颗粒物模拟样品分析结果表明,本方法精度高、结果准确、分析速度快,可满足核保障监督、禁产核查和核取证中含钚颗粒物直接分析的需求.     

242Pu为稀释剂电感耦合等离子质谱定量分析237Np的可行性理论研究

研究了以242Pu为稀释剂时,电感耦合等离子质谱(ICP-MS)定量分析237 Np的理论可行性。研究结果表明:237 Np和242Pu灵敏度的差异主要是由两者电离度的差异和质量歧视效应引起的。在等离子体温度为7 000～10 000K和样品提升率为50～1 000μL/mL时,经过质量岐视校正后,237 Np和242Pu灵敏度的差异只在于两者电离度的差异,且两者相对差异<1%。以242Pu为稀释剂ICP-MS定量分析237 Np的方法在理论上是可行的。     

天然的镎

原子核物理学的成就,使我们能够用合成的方法获得新的放射性元素。超铀元素(即原子序数超过92的元素)的合成有着巨大的实际意义。它们在制取原子能的过程中起看重大的作用。 _(92)铀~(238)的原子和慢速中子互相作用可产生_(92)铀~(239),后者进一步蜕变而生成二个新元素——镎(Np)和钚(Pu)。 _(92)铀~(238)的这些变化按照下式进行: _(92)U~(238)+_0n~1→_(92)U~(239)→β→_(93)Np~(239)→β→ _(94)Pu~(239) 在1200℃左右的温度下,以金属钡的蒸气处理镎的氟化物也可以得到微量的镎。纯镎是银白色     

多接收电感耦合等离子体质谱在单个铀颗粒物分析中的应用研究

为准确地获取单个铀颗粒物中具有核保障监督和核取证意义的铀同位素组成信息和~(230)Th/~(234)U比值,本研究基于多接收电感耦合等离子体质谱(MC-ICP-MS),建立了不同粒径铀颗粒物中铀同位素比值的测量方法和不经化学分离纯化流程的~(230)Th/~(234)U分析技术。在评估铀钍本底的基础上,采用外标法校正同位素的质量分馏效应,进样0.40 ng/g的天然铀工作溶液跳峰测量离子计数器检测效率,使用已知铀钍比例的标样校正铀钍响应差异,完成分析方法的不确定度评估。结果表明,化学处理过程引入的~(238)U和~(232)Th分别小于8×10~(-5)ng和1.5×10~(-3)ng,MC-ICP-MS对粒径0.5~5.0μm铀颗粒物中~(235)U/~(238)U测量的相对扩展不确定度3.6%(k=2),主要来自本底扣除引入的不确定度和B类不确定度;对粒径5μm铀颗粒物中~(235)U/~(238)U测量的相对扩展不确定度0.2%(k=2),主要来自法拉第杯检测器对弱信号测量的不确定度;对更大粒径铀颗粒物中~(234)U/~(235)U和~(236)U/~(235)U测量的相对扩展不确定度分别小于3.5%和3.8%(k=2),主要来自B类不确定度。不经铀钍分离纯化流程,MC-ICP-MS可测得粒径几十微米铀颗粒物中~(230)Th/~(234)U比值信息,并诊断浓缩铀颗粒物生产年龄。     

萃取色层-ICP-MS法测定金属钚中杂质元素

采用HNO_3(1+1)和少量HF溶解金属钚,建立了利用TEVA(三烷基甲基胺盐,烷基为C8-C10)分离大量Pu中微量Zr等杂质元素,ICP-M S分析的方法。采用H_2O_2调节Pu的价态,样品在3 mol/L HNO3上柱-3 mol/L HNO_3淋洗Zr等杂质元素,并利用ICP-MS测量了分离后样品中Zr,Mo,Ru等杂质元素的含量。结果表明,Pu的去污系数达到104,Zr等24种杂质元素加标回收率多为90%~115%,相对标准偏差优于15%(n=6),方法的检测限为0.2~150 ng/g(以Pu计)。     

First results studying the transmutation of 129I, 237Np, 238Pu, and 239Pu in the irradiation of an extended natU/Pb-assembly with 2.52 GeV deuterons

An extended U/Pb-assembly was irradiated with an extracted beam of 2.52 GeV deuterons from the Nuclotron accelerator of the Laboratory of High Energies within the JINR in Dubna, Russia. The lay-out of this experiment and first results are reported. The Pb-target (diameter 8.4 cm, length 45.6 cm) is surrounded by a ^natU-blanket (206.4 kg) and used for transmutation studies of hermetically sealed radioactive samples of ¹²⁹I, ²³⁷Np, ²³⁸Pu and ²³⁹Pu. Estimates of transmutation rates were obtained as result of measurements of gamma-activities of the samples. Information about the spatial and energy distribution of neutrons in the volume of the lead target and the uranium blanket was obtained with sets of activation threshold detectors (Al, Y and Au) and solid state nuclear track detectors (SSNTD). An electronic ³He neutron detector was tested on-line. A comparison of experimental data with theoretical model calculations using the MCNPX program was performed yielding satisfactory results. Collaboration “Energy plus Transmutation” This work is dedicated to the cherished memory of Professor Vladimir Pavlovich Perelygin from the JINR in Dubna, Russia.     

Determination of 17O and 18O isotopic abundances in 238Pu materials by γ-ray spectrometry

A procedure has been developed for nondestructive determinations of ¹⁷O and ¹⁸O isotopic abundances in ²³⁸PuO₂ fuels produced for biomedical application. Close control of these isotopes is important because they increase the neutron emission rate caused by (α, n) reactions. γ-Rays accompanying these reactions are measured by a lithium-drifted germanium [Ge(Li)] detector and related to their respective isotopic abundances. Each determination has a detection limit approximating the lowest contents encountered in PuO₂ samples of 0.005% ¹⁷O and 0.001% ¹⁸O. The average deviations for each determination are estimated to be about ±25% at their detection levels, and less than ± 10% for abundances above 0.01%.     

Using low resolution gamma detectors to detect and differentiate 239Pu and 235U fissions

When ²³⁹Pu and ²³⁵U undergo thermal neutron-induced fission, both produce significant numbers of beta-delayed gamma rays with energies in the several megaelectron volt range. Experiments using high energy-resolution germanium detectors have shown that it is possible to distinguish the fission of ²³⁹Pu from that of ²³⁵U. It is desirable to detect the presence of ²³⁵U or ²³⁹Pu using detectors that are less expensive and more rugged than high purity germanium detectors. To this end we demonstrate how differences in the energy spectrum and decay rates of the beta-delayed gamma rays can be used to identify ²³⁹Pu and ²³⁵U using low resolution plastic and liquid scintillator detectors. Experimental data are used to identify differences in the spectra and also to test the identification algorithms. Results to date are very promising.     

Evaluation of measurements of 238Pu, 239Pu and 240Pu in urine at the microbecquerel level using thermal ionization mass spectrometry and alpha-spectrometry at Los Alamos National Laboratory: Results of a two year comparison test (LA-UR-06-8055)

The Intercomparison Studies Program (ISP) at the Oak Ridge National Laboratory (ORNL, Oak Ridge, TN, USA) provides natural-matrix urine quality-assurance/quality-control (QA/QC) samples to radiobioassay analysis laboratories. In 2003, a single laboratory (Los Alamos National Laboratory LANL, Los Alamos NM USA) requested a change in the test-samples provided previously by the ISP. The change was requested to evaluate measurement performance for analyses conducted using thermal-ionization mass spectrometry (TIMS). Radionuclides included ²³⁹Pu at two activity levels (75–150 μBq^·sample⁻¹ and 1200–1600 μBq^·sample⁻¹) and ²³⁸Pu (3700–7400 μBq^·sample⁻¹). In addition, ²⁴⁰Pu was added to the samples so that the ^239+240Pu specific activity was 3700–7400 μBq^·sample⁻¹. In this paper, the results of testing during the period May, 2003 through September, 2005 are presented and discussed.     

A direct determination of 239Pu in femtomole range in aquatic solution by neutron activation

Summary A method is presented which facilitates the direct determination of ²³⁹Pu in aquatic solution by the (n,f) reaction with reactor neutrons and subsequent gamma spectrometry without chemical elaboration. Trace impurities of water constituent heavy metal elements are simultaneously determined through their (n, ) reactions. The sensitivity attained by this method is 1.6×10^–15 mol/l ²³⁹Pu by measuring the fission product pairs ¹³²Te/¹³²I or ¹⁴⁰Ba/¹⁴⁰La. The trace impurities determined in the range of 10^–810^–13 mol/l give an insight into the chemical behaviour of Pu in a given water. The natural uranium concentration plays a role to limit the Pu determination on the one hand and to help understanding the chemical behaviour of Pu on the other hand.

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Direkte Bestimmung von ²³⁹Pu in wäßriger Lösung im Femtomol-Bereich mit Hilfe der Neutronenaktivierung

Zusammenfassung Es wird eine Methode vorgestellt, die die direkte Bestimmung von ²³⁹Pu in wäßriger Lösung über die (n,f)-Reaktion mit Reaktorneutronen und mit anschließender gammaspektrometrischer Messung ohne chemische Aufbereitung ermöglicht. Spurenverunreinigungen der im Wasser enthaltenen Schwermetallelemente werden gleichzeitig über ihre (n, )-Reaktionen erfaßt. Durch die Messung der Spaltproduktpaare ¹³²Te/¹³²I oder ¹⁴⁰Ba/¹⁴⁰La wird bei dieser Methode eine Nachweisgrenze von 1,6×10^–15 mol/l ²³⁹Pu erreicht. Die bestimmten Spurenverunreinigungen im Bereich von 10^–8 bis 10^–13 mol/l geben einen Einblick in das chemische Verhalten von Pu in einem vorliegenden Wasser. Der natürliche Urangehalt spielt auf der einen Seite eine einschränkende Rolle bei der Pu-Bestimmung, trägt aber auf der anderen Seite zum Verständnis des chemischen Verhaltens von Pu bei.

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Dedicated to Prof. Dr. K. H. Lieser on the occasion of his 65th birthday     

137Cs, 40K, 90Sr, 238, 239+240Pu, 241Am and 243+244Cm in forest litter and their transfer to some species of insects and plants in boreal forests: Three case studies

Results for ¹³⁷Cs, ⁴⁰K, ⁹⁰Sr, ^238,239+240Pu, ²⁴¹Am and ^243+244Cm measurements in plant, insects and forest litter samples collected at three sites in Poland are presented. New results are compared with some existing data for locations examined during previous studies. Insect samples were introduced now for the first time. Relatively high activities of ⁹⁰Sr were noticed for spruce bark beetle (Ips typographus) and those for ¹³⁷Cs, plutonium and ²⁴¹Am for forest dung beetle (Anoplotrupes stercorosus). Faster than caused by physical decay decrease of radiocesium activity was noticed for the majority of plant and litter samples. The results for ^239+240Pu for litter were similar to previous results, but the activities of ²³⁸Pu were smaller. The activity ratio between ²⁴¹Am and ^239+240Pu was found lower than expected for known proportions between global and Chernobyl fallout. Thus a kind of dynamic behavior of Pu and Am in the forest ecosystem is concluded. Transfer factors and aggregation coefficients were estimated and discussed for both plants and insects as well as between insects and the part of plants (or litter) they feed on. Many of them were never presented before.The authors are thankful to the Polish State Committee for Scientific Research for financial support of this investigation, Grant No. PG04 07520.     

Measurement of the radioactivity of 238U, 226Ra, 210Pb, 228Th, 232Th, 228Ra, 137Cs and 40K in tea using gamma-spectrometry

The aim of the present work was to determine the concentration of radionuclides in all kinds of tea available at the local Egyptian market. Radioactivity of the nuclides ²³⁸U, ²²⁶Ra, ²¹⁰Pb, ²²⁸Th, ²³²Th, ²²⁶Ra, ¹³⁷Cs and ⁴⁰K were measured in tea by direct γ-ray spectrometry using HPGe detector and their mean values were 16.0±5.3, 3.1±0.7, 34.3±3.4, 3.4±1.2, 3.0±0.6, 3.1±0.8, 0.9±0.2 and 623±25 Bq·kg⁻¹, respectively.     

Die Bestimmung von 175Hf, 172Hf, 172Lu und 169Yb

Ohne Zusammenfassung     

CAS SCF Cl calculations for the 3Σ−g, 1Σ+g, 3Σ+u, and 5Δu states of Sc2

CAS SCF CI (SD) calculations have been carried out for the ³Σ^?_g, ¹Σ⁺_g, ³Σ⁺_u, and ⁵Δ_u states of Sc₂ using large gaussian basis sets. The ³Σ^?_g, ¹Σ⁺_g, and ³Σ⁺_u states arise from the ²D(4s² 3d¹) + ²D(4s² 3d¹) limit of Sc₂ and are found to be only weakly bound (D_c ≈ 0.06 eV and R_c ≈ 8.0a₀). The ⁵Δ_u state arises from the ²D(4s² 3d¹) + ⁴F(4s¹ 3d¹ 4p¹) atomic limit. This state is found to be strongly bound relative to its limits (D_c ≈ 0.8 eV and R_c ≈ 7.0a₀).