可活化稳定同位素示踪-中子活化分析法研究育龄妇女膳食铁的生物利用率

采用两种浓缩丰度分别为 61 4%和 2 3 4%的可活化稳定浓缩同位素54 Fe和58Fe作为示踪剂 ,结合中子活化分析法研究了北京地区健康育龄妇女膳食铁的生物利用率 ,并以原子吸收分光光度法测定粪便排出的总铁和以不易被吸收的镝元素监测浓缩同位素铁在体内的滞留时间以确定不同试验者的粪便收集次数等多种途径来提高分析结果的可靠性。研究结果显示 ,受试妇女膳食铁的生物利用率为(1 4 9± 3 9) %。     

^41Ca示踪-AMS法测定细胞胞浆内Ca^2＋浓度的方法研究

^41Ca示踪剂是理想的生物医学示踪剂。本工作首次将^41Ca示踪剂用于测定在石棉作用下引起人肺成纤维细胞(HLF)胞浆钙离子浓度。采用体外培养的HLF作为研究对象，用石棉进行染毒，用超声破碎离心提取细胞胞浆制备生物样品，并对样品进行加速器质谱(AMS)测量。研究结果初步证明可将^41Ca示踪-AMS法用于石棉作用下HLF细胞的胞浆钙离子浓度分析。该方法有可能应用于生物学领域，为深入研究生命活动的机理提供分析手段。     

从60 MeV/u18O离子辐照过的钍中分离Ra

对以^212Pb,^133Ba和^224Ra比作示踪剂，（NH4）2H2EDTA为淋洗剂，用阳离子交换法从Pb、Ba中分离Ra的工艺条件做了研究。提出了一个从60MeV／u ^18O离子辐照过的ThO2靶中分离Ra的放射化学流程。实验结果表明，该流程对主要反应产物，特别是Ba的去污较好，Ra的产额可达70％以上。     

沉淀法分离Cs和Rb的研究

以^137Cs和^86Rb为示踪剂对硅钨酸铯和碘铋酸铯两种沉淀法分离Cs和Rb进行了研究。结果表明,碘铋酸铯沉淀法比硅钨酸铯沉淀法分离效果好;采用亚化学计量的碘铋酸钾分离时,Cs沉淀率可达70％～80％,Cs、Rb的分离因数大于100。     

枸橼酸镓-~(67)Ga的制备

采用自制的磷酸三丁酯（TBP）萃淋树脂作交换柱,应用反相分配色层法研究了^67Ga与靶材料中Zn,Cu,Ni等元素及活化产物^65Zn,^56Co,^57Co的分离,建立了一个简便、快速生产枸橼酸镓－^67Ga的方法。所得^67Ga的放射性核纯达99．5％,每37MBq^67Ga中其它金属离子总量不超过2．5μg。     

锌同位素丰度比测量中的几个关键问题

采用多接收-电感耦合等离子体质谱仪(MC-ICP-MS)和多接收-热电离同位素质谱仪(MS-TIMS)对溶液中锌同位素丰度比测量结果进行实验室间比对,5个样品68Zn与66Zn的丰度比为0.02~15.00。比对结果显示,5个实验室的测量结果相符性较差,测量不确定度为1.29%~0.03%(以64Zn/66Zn为例),呈现与样品丰度比相关的趋势,相同仪器测量结果的不相符性主要受是否扣除空白及扣除的准确性影响。另外,MC-ICP-MS系统误差校正条件也影响测量的准确性,MC-ICP-MS质量歧视校正系数为非线性。     

计算机模拟γ测量谱

一个建立在微机DOS环境下的计算机模拟γ射线测量谱系统以一个实测的^135Cs谱作为模板,对活化测量谱和同位素源的γ射线谱进行了成形模拟。谱中包含了对全能峰、康普顿沿、康普顿坪和反散射峰的模拟。模拟系统具有谱峰面积计算、谱成形、谱显示、谱处理、谱存盘等功能。利用该模拟程序对^137Cs源、^152Eu源、^60Co源的γ射线谱以及锆样品和岩石样品的中子活化测量谱进行了模拟,模拟谱与实际测量谱非常接近。     

3H、Br-在原状黄土柱中迁移的实验室研究

采用脉冲方式将惰性示踪剂^3H和Br^-同时或单独注入原状黄土柱中,华而不实两种示踪剂的迁移状况。结果表明Br^-比^3H迁移速度快,阴离子排斥效应可能是其主要原因。     

含铯废水膜处理工艺中吸附剂的选择

在含铯废水无机离子交换吸附-微滤膜处理工艺的吸附剂研究中,以134Cs为示踪剂研究了蒙脱石、蛭石及亚铁氰化锌钾对Cs的吸附效果以及体系各种因素对吸附的影响。依据研究结果,结合絮凝沉淀和中空纤维膜微滤一体化处理工艺（CMF）运行参数,从中筛选出亚铁氰化锌钾作为含铯废水膜处理工艺中的吸附剂,初步确定吸附剂投加量为0.33g/L。     

252Cf中子活化核燃料棒235U富集度均匀性检测装置

采用^252Cf中子活化方法研制燃料棒^235U富集度均匀性检测设备，用慢化后的^252Cf中子照射燃料棒，使燃料棒UO2芯块中的^235U发生裂变，通过测量其裂变产物的γ射线总强度对燃料棒^235U富集度及其均匀性进行在线检测。采用1．2mg的^252Cf中子源，能检测出燃料棒中^235U富集度相对偏差土10％的单个混料芯块，单根燃料棒的检测速度可达7m/min，检测结果的置信概率为97．74％。     

Zinc Isotope Fractionation on Benzo-15-crown-5 Resin by Liquid Chromatography

Chromatographic fractionation of zinc isotopes was performed on the synthesized benzo-15-crown-5 resin as a column packing material at 323K in the breakthrough manner for both a frontal and a rear bands. Zinc adsorption capacity was affected by anion chloride concentration and solvent dielectric constant. The heavier zinc isotopes were found enriched to the solution phase and the lighter zinc isotope was concentrated on the resin phase. The frontal maximum enrichment ratio for isotopic pair of ⁶⁸Zn/⁶⁴Zn was 1.0081. The isotope separation coefficients for isotopic pair of ⁶⁸Zn/⁶⁴Zn for frontal and rear band, were 5.3 × 10^?4, 4.5 × 10^?4, respectively.     

Research of Radioisotope Production with Fast Neutrons, (VI)

Copper-67, the longest-lived radioisotope of copper, was prepared by using the reaction ⁶⁷Zn(n p,)⁶⁷Cu. Zinc enriched in ⁶⁷Zn up to 93.4% was irradiated in JRR-1 reactor for 5hr with a fast neutron flux of 1.5×10¹²n/cm²/sec. Copper-67 formed in the zinc target was separated by anion exchange separation using the chloro-complex of the metals. The yield of ⁶⁷Cu and radiochemical impurity were investigated. Seventeen millimicrocuries of ⁶⁷Cu was obtained from 1mg of zinc. No radioactive impurities other than ⁶⁴Cu were not found. Even with the use of enriched target, a more ^MCu was produced than ⁶⁷Cu. The proportion of ⁶⁷Cu to total copper radioactivity was 26% immediately after the irradiation.     

微堆超热中子活化分析在地学样品测定中的应用

微型中子源反应堆(简称微堆)是以高浓铀(235 U)作燃料的轻水欠慢化型反应堆,辐照孔道内存在有较大份额的超热中子和快中子,适合进行超热中子活化分析(ENAA)的实验研究。地质样品成分复杂,在用普通的中子活化分析时,基体元素影响了部分元素的准确测定。为降低基体成分的本底干扰、改善目标元素的测量精密度和检出限,可采用超热中子活化分析的方法。本文利用微堆上安装的屏蔽材料为镉的超热中子辐照孔道,测定了元素周期表中67种元素的约130个核素的镉比,讨论了在超热中子活化分析中某些元素的有利因子及铀裂变和(n,p)反应的干扰情况,验证了微堆ENAA方法在地质科学样品检测中的实际应用,证实利用本方法可测定地学样品中20余种元素,其检出限、精密度和准确度均得到了较明显的改善。该法是常规活化分析方法必要的、有益的补充。     

Pu-breeding feasibility in PWR

This study addresses the issue of alternative pathways for breeding plutonium in a 900 MWe three loop thermal pressurized water reactor (PWR), either fueled with uranium fuel (3.5% U-235) or with mixed fuel (20% MOX). During the operation of a nuclear reactor the in-core neutron flux and the ex-core neutron flux are monitored with flux detectors. At the places where those detectors operate, the guide thimbles and the vessel wall, respectively, the neutron flux can be used to irradiate material samples. This paper investigates whether it would be possible to produce plutonium by breeding it at the walls of a PWR vessel and/or in the guide thimbles. The neutron flux in the reactor and the corresponding multi-group spectra are estimated with Monte Carlo simulations for different positions at the vessel wall of a PWR operating with either UO₂ or MOX. Then the irradiation of fresh uranium samples at the vessel wall and in the guide thimbles are calculated and the isotopic composition of the irradiated samples are determined. The minimum irradiation period and the necessary minimum amount of fresh uranium to breed different grades of plutonium are derived.     

活化法测量CFBR-II堆中子注量和中子能谱

采用活化法研究了CFBR-II堆中子能谱、中子注量分布和辐照样品对中子场的扰动。建立了用于求解中子能谱的SAND-II解谱程序。对实验结果的分析表明,活化法得到的中子注量率与裂变室得到的结果是一致的,辐照样品对中子能谱有一定的软化。     

活化法测量散裂靶中子能谱的实验验证

散裂靶中子的能谱对加速器驱动次临界系统的倍增因数和嬗变率等影响很大,计算表明散裂靶中子谱在MeV能区与裂变中子谱相近。本文利用活化法测量临界装置的泄漏中子谱和中子注量率,提出了用In、Al、Mg、Ti、Au、Zn、Ni、Rh、Fe和Co等活化箔测量散裂靶中子能谱和中子注量率的方案。结果表明,将活化箔在散裂靶中子场中辐照5h,中子注量最高达5×1014 cm-2量级,辐照后1h内取出活化箔,根据半衰期的长短安排测量顺序,可测量散裂靶的中子能谱和中子注量率。     

Production of high-purity medical radio isotope 64Cu with accelerator-based neutrons generated with 9 and 12 MeV deuterons

We conducted a feasibility study for producing a high-purity medical radioisotope ⁶⁴Cu from natural zinc with accelerator-based neutrons. ⁶⁴Cu isotopes were produced via the ⁶⁴Zn(n,p) reaction. The accelerator-based neutrons were generated via the C(d,n) reaction using low-energy deuterons of 9 and 12 MeV on a 1-mm-thick carbon target. First, the production purity was estimated using the evaluated nuclear data library JENDL-4.0 and our previously measured thick target neutron yield. We found that even when natural zinc was used as the starting material, significantly high-purity ⁶⁴Cu could be obtained. Next, irradiation experiments for producing ⁶⁴Cu using natural zinc were conducted at Kyushu University Tandem Laboratory, with the amounts of ⁶⁴Cu isotopes and other gamma-emission nuclides measured by a high-purity germanium detector. As a result, high-purity ⁶⁴Cu isotopes of 1.11(49) × 10⁰ and 3.70 (17) × 10⁰ Bq/g/μC were produced with incident deuteron energies of 9 and 12 MeV, respectively.     

可燃毒物铒的辐照及其同位素热电离质谱法测定

铒(Er)是一种适用于轻水堆(LWR)的长效可燃毒物,Er_2O_3的堆内辐照是研究中子毒物Er辐照性能的基本手段。Er_2O_3在高通量工程试验堆(HFETR)中子注量率约为2×10~(14)/(cm~2·s)的辐照孔道中辐照91.3h。采用热电离质谱法(TIMS)测定辐照前、后样品中Er同位素丰度,跳峰模式测定6个Er同位素,低丰度~(162)Er由法拉第杯检测。测定时准确控制升温测量电流,将蒸发带和电离带电流控制在1 400、5 500mA以下,可减小~(168)Yb、~(170)Yb对~(168)Er、~(170)Er的同量异位素影响。结果表明,经中子辐照后~(166)Er、~(167)Er、~(168)Er同位素丰度变化较大,丰度变化与中子吸收截面大小密切相关。     

利用252Cf源对镍精矿进行中子活化分析

利用MCNP模拟改进了中子活化分析的装置，并采用中子产额较高的^252Cf作中子源，对镍精矿样品和标准样品进行照射；利用相对测量法对用高纯锗探测器得到的镍精矿和标准样品的活化能谱进行能谱处理，得到镍精矿的元素成分和含量。结果显示，^252Cf中子源中子活化在线分析可以较好地满足工业要求。