土壤样品中^90Sr的准确分析测定

^90Sr是环境中一种重要的人造放射性核素。因其裂变产额高且为中长寿命核素，生物半衰期长，具亲骨性，是核环境监测中的一种重要核素，因此，对环境土壤样品中^90Sr的准确分析对安防、环保有着十分重要的意义。     

93Zr的放化分离方法和半衰期测量研究

93Zr是一长寿命裂变产物核素，在各种不同的可裂变材料中的裂变产额值都较高。     

熔岩玻璃体核素衰变热功率的计算

温度是影响熔岩玻璃体溶解速度的关键因素,为此,本文计算了核试验后10~300 000d内熔岩玻璃体中核素衰变热功率,评估了核素衰变热功率对熔岩玻璃体的温度和溶解速度的影响程度。采用了国际原子能机构给出的100kt TNT当量地下核试验产生的、半衰期大于1a的放射性核素含量,利用其中裂变产物核素137 Cs的含量推算累积裂变产额大于0.1%、半衰期为1d~1a的短寿命裂变产物核素的含量。分析了各核素的放射性衰变特点,采用ENDF/BⅦ库中核素衰变辐射的平均α能量、平均电子能量和平均电磁辐射能量计算各核素在熔岩玻璃体内因衰变而沉积的能量。计算结果表明:核素衰变热功率呈分段幂函数衰减;在10~2 000d、2 000~60 000d和60 000d之后的时段内,衰变热功率分别主要源于短寿命裂变产物核素、长寿命裂变产物核素和锕系元素。核素衰变热功率对熔岩玻璃体的温度和溶解速度的影响不大,1 000d后影响非常小。     

不加载体分离^126Sn的方法研究

~(126)Sn是一长寿命裂变产物核素,它在不同裂变体系中都有不可忽略的裂变产额,如~(235)U热中子裂变产额为5.59×10~(-2)％,快中子裂变产额为1.39×10~(-1)％,高能中子裂变产额为1.76％。在高放废液处理处置研究中,对~(126)Sn需予以考虑。     

从Purex流程硝酸废液中提取锝的工艺研究

<正>~(99) Tc是乏燃料中主要的长寿命裂变产物之一,半衰期为2.11×10~5 a,在热中子辐照下235 U裂变产额约为6%,在乏燃料中的含量约为0.1%。~(99) Tc是核燃料放射性废物处置中难以处理的核素,其在地质条件以及生物圈中具有较强的迁移性,因此其地质处置将给生物圈带来潜在的长期放射性危害风险。~(99) Tc最安全的处置方式是分离-嬗变,通过(n,γ)反应使其转变为稳定或短寿命的     

企业标准《尿中^90Sr的分析方法》的编制

^90Sr是纯β放射体，半衰期为29．1a。^90Sr裂变产额较高，对^235U热中子诱发裂变，产额为4．79％。^90Sr作为辐射源在军事、科学研究、放射仪表上均有重要用途。锶是典型的亲骨性核素，^90Sr、^89Sr分别属于高毒性和中毒性核素，在体内具有极大危害。     

Determination of ^129I in IAEA-375 Reference Material

^79Se是一长寿命、纯β裂变产物核素，β能量为0．151MeV。^79Se半衰期已被测量过5次，每次测得数据间在误差范围内不吻合。随着新的测量手段的不断涌现，对^79Se半衰期重新进行测量很有必要。     

放化法测量~（79）Se的半衰期

长寿命裂变产物核素￣（７９）Ｓｅ的半衰期还没有被准确地测量过，文献中一直引用１９４９年测定的值：Ｔ＿（１／２）≤６．５×１０￣４ａ。本工作应用放化法测量了￣（７９）Ｓｅ的半衰期。从中子照射的铀靶中分出放化纯的￣（７９）Ｓｅ，并用液闪谱仪测量其活度。利用￣（９０）Ｓｒ、￣（１３７）Ｃｓ作为监测核计算出铀靶的裂变数，然后根据裂变产额得到￣（７９）Ｓｅ核数。得到的￣（７９）Ｓｅ的半衰期为（４．８±０．４×１０￣５ａ。）     

^142La的放化分离方法研究

为了提高对核燃料微裂变过程诊断的灵敏度,要求使用短寿命裂变产物核素。142La就是适合的核素之一。但其现有衰变数据的准确度较差,需要对它进行更精确的测量。要获得准确的数据必须制备出纯的核素。 裂变产物是一个很复杂的体系,选择适当的辐照、冷却、分离、测量时间可以把干扰同位素的含量降低甚至消除,达到部分同位素分离的目的。 影响142La测量的主要同位素有141La和143La。其中,142La母体142Ba的半衰期（T1/2=10.6 min）远大于143La母体143Ba的半衰期（T1/2=14.7s）。235U经中于辐照后,冷却 3～5 min,143Ba全部     

针对裂变产额和半衰期的燃耗计算灵敏度和不确定度分析方法

基于广义微扰理论推导了裂变产额和半衰期的燃耗灵敏度系数理论模型,该模型考虑了原子核密度和中子通量的相互影响,并开发了燃耗计算中有效增殖因数和原子核密度等响应参数对核数据的灵敏度和不确定度分析程序。基于评价核数据中裂变产物独立产额的标准差数据,产生了针对压缩燃耗数据库的裂变产额协方差矩阵,以提高不确定度的计算精度。基于ENDF/B-Ⅶ.1数据库量化了UAM基准题TMI-1栅元无限增殖因数及重要裂变产物和重核的原子核密度由裂变产额和半衰期引入的不确定度。数值结果表明,对于栅元无限增殖因数,裂变产额和半衰期引入的不确定度很小;对于部分裂变产物的原子核密度,裂变产额和半衰期会引入较大的不确定度。     

一种铅-铋合金冷却快堆的高放废物积累量研究

目前商用压水堆积累了大量的长寿命高放废物,放射毒性强,衰变时间漫长,对环境和人类构成了长期威胁,作为6种第四代核能系统堆型中的一种,铅基冷却快堆在减少长寿命高放废物产生方面具有优势。基于此本文提出了一种热功率为300 MW的铅-铋合金冷却快堆设计。利用MCNP程序对反应堆堆芯进行建模并计算了堆芯在寿期初的主要物理参数,详细分析了燃耗过程中长寿命高放核素的积累量,并与一般压水堆长寿命高放核素的积累量进行了比较。结果表明,对主要关心的次锕系核素,铅-铋合金冷却快堆的产生量远小于压水堆的,而长寿命裂变产物的产生量与压水堆的相当。总体来说,铅-铋合金冷却快堆产生的长寿命高放废物总量小于压水堆的,可看出铅-铋合金冷却快堆在减少长寿命高放废物产生方面更具有竞争性。     

Gamma-ray and half-life data for the fission products

Presented here are gamma-ray and half-life data for the fission products. The first table lists the energies and intensities of up to 5 of the more abundant gamma rays for each fission product. The second table lists gamma rays in order of increasing energy. The first section of this table covers nuclides with half-life less than one hour. The second section covers nuclides with half-life greater than one hour. Each listing consists of gamma-ray energy, intensity, and half-life. The third table lists all the fission products in order of increasing mass. Data for each nuclide include half-life, uncertainty and reference key for half-life, number of gamma rays, reference key for gamma data, total gamma-decay energy (including internal-conversion energy), and internal-conversion energy expressed as fraction of total gamma-decay energy.References available through January 1977 have been covered.     

Was the Chazhma Accident a Chernobyl of the Far East?

The 1985 reactivity accident on a submarine in bukhta Chazhma was accompanied by a substantial emission of fission products and activational radionuclides whose total activity reached 5 MCi. Some specialists have compared this emission to the emission resulting from the 1986 accident in Chernobyl, neglecting the large difference in the radionuclide composition: short-lived products of prompt fission of uranium (with an admixture of activational ⁶⁰Co) in Chazhma and long-lived fission products accumulated over the run of the power reactor with an admixture of short-lived nuclides from the spontaneous excursion of the RBMK-1000 reactor in the Chernobyl nuclear power plant. It is shown that the emission of long-lived radioecologically significant radionuclides in Chazhma was approximately 0.79 Ci, while in the Chernobyl accident this emission was 90 MCi.A quantitative comparison is presented of the activity and radionuclide composition between the accidents in Chazhma and Chernobyl taking account of the fraction of long-lived radionuclides and neglecting the radioactive inert gases. These quantitative estimates are used to show that the Chazhma accident is not analogous to the 1986 accident in Chernobyl.     

Feasibility of Fast Fission System Confining Long-Lived Nuclides

The feasibility of fast fission system confining long-lived nuclides without other supporting system as synergetics for fuel sustainment and waste incineration was studied from the aspects of nuclear material balance and neutron economy. The continuous utilization of fast fission system which confines all actinides in the reactor but discharges all FP will lead to huge accumulation of radioactive wastes such as ¹²⁹I, ¹³⁵Cs, ¹⁰⁷Pd, ⁹³Zr, ⁹⁹Tc, ¹²⁶Sn and ⁷⁹Se in the far future. Then we studied the feasibility of the system that these long-lived seven FP are also confined in the reactor with actinides. In this scheme, all the long-lived nuclides to be disposed of were exposed with neutrons in the reactor and removed as different nuclides after nuclear transmutation. As the wastes stored in the repository was composed of only shorter-lived nuclides, total amount of radioactive wastes in the repository was suppressed to be less than a few tons per 3 GWt reactor.     

钚及其裂变产物钯 、银 、镉 、锡 、锑 、锆的系统分离方法

描述了钚及其6种裂变产物钯、银、镉、锡、锑、锆的系统分离方法：在强碱性阴离子交换树脂柱上将盐酸介质的辐照靶溶解液中的这些元素分为5组,然后再针对各组目标元素进行分离和纯化,可简便快速地从同一份靶溶解液中分离以上7种元素。采用辐照铀靶对分离方法进行了验证,结果表明,分离流程对6种裂变产物的化学回收率均大于70%,对γ谱仪测量干扰的主要核素去污因子均大于1.0×10³,可满足²³⁹Pu裂变谷区核素裂变产额测量对化学分离的要求。     

钚及其裂变产物钯、银、镉、锡、锑、锆的系统分离方法

描述了钚及其6种裂变产物钯、银、镉、锡、锑、锆的系统分离方法：在强碱性阴离子交换树脂柱上将盐酸介质的辐照靶溶解液中的这些元素分为5组，然后再针对各组目标元素进行分离和纯化，可简便快速地从同一份靶溶解液中分离以上7种元素。采用辐照铀靶对分离方法进行了验证，结果表明，分离流程对6种裂变产物的化学回收率均大于70%，对γ谱仪测量干扰的主要核素去污因子均大于1.0×10³，可满足²³⁹Pu裂变谷区核素裂变产额测量对化学分离的要求。     

239Pu(nth,f)短寿命裂变产物产额测量

采用γ能谱相对测量方法,以97Zr为内标参考核素,完成了239Pu(nth,f)短寿命裂变产物88 Rb、95 Y、101 Mo、101 Tc、138 Csg、142 La等核素的累积产额测量。实验测得88 Rb、95 Y、101 Mo、101 Tc、138 Csg、142 La的累积产额数据分别为(1.32±0.05)%、(4.69±0.22)%、(6.13±0.32)%、(6.10±0.22)%、(6.24±0.24)%、(4.74±0.17)%。对高纯锗探测器中高能端效率刻度、样品封装与辐照、γ谱测量几何条件设计、γ谱测量与数据分析进行了研究。实验测量裂变产物核素分别位于非对称裂变质量分布双驼峰曲线轻峰的左侧、中部和右侧,重峰的中部与右侧。     

Study on MA and FP transmutation in fast reactors

Feasibility studies have been performed to develop an optimized fast reactor core for reducing long-term radiotoxicity of nuclear waste by minor actinide(MA) and long-lived fission product(FP) transmutation, taking into consideration fuel cycle technology. Systematic parameter survey calculations were implemented to investigate the basic characteristics of MA and FP transmutation in a fast reactor core. The hybrid MA-loading method, where Np nuclide is dispersed uniformly in the core and target subassemblies containing Am, Cm and rare earth nuclides are loaded into the blanket region, has the potential to achieve the maximum transmutation of MA with no special fuel design considerations. The introduction of target subassemblies using duplex pellets - a moderator annulus surrounding a ⁹⁹Tc core - has a great potential to transmute long-lived fission products in the radial blanket region of the fast reactor core.     

Yield of long-lived fission product transmutation using proton-, deuteron-, and alpha particle-induced spallation

The transmutation of long-lived fission products through spallation induced by light nuclides was investi-gated for the purpose of determining the feasibility o...     

衰变对严重事故条件下裂变产物释放及场外剂量评价影响分析

介绍了某三代核电厂严重事故释放类别,选取会造成大量放射性释放的释放类别和对应的典型严重事故序列,采用MAAP程序计算分析裂变产物向环境释放特性。在此基础上,选取对人员剂量贡献最大的几种核素,计算考虑衰变和不考虑衰变2种情况下,各核素向环境累积释放活度及场址边界500?m处的全身剂量和甲状腺剂量的大小,并分析了衰变对累积释放活度和剂量评价的影响。结果表明:衰变对裂变产物向环境累积释放活度的影响与核素半衰期及事故后开始向环境释放时间有关;半衰期越短,裂变产物开始向环境释放时间越晚,衰变的影响越明显;从场外剂量分析,衰变对全身剂量的影响较甲状腺剂量的影响更明显。