Pu材料γ能谱分析软件CMGA2.0

在92～112keV区间内,Pu材料的多通道γ能谱共包含²³⁸Pu、²³⁹Pu、²⁴⁰Pu、²⁴¹Pu和²⁴¹Am自发衰变发出的8条γ射线和29条X射线。CMGA通过分析该区间能谱,可给出样品中Pu同位素丰度。升级后的CMGA（2.0版）对2例样品6次重复测量的能谱进行分析,其给出的²⁴⁰Pu与²³⁹Pu含量的比值分别为质谱分析结果的1.010±0.008和0.995±0.011。通过对比CMGA2.0使用不同本底描述方法得到的92～105keV区间能谱拟合图,可看出双线性积分步本底函数可更好地描述复杂重峰下的本底。     

固定化马尾藻生物吸附239Pu实验研究

采用藻酸钙作为载体对马尾藻生物吸附剂进行固定化处理,并通过静态和动态实验法对固定化马尾藻生物吸附剂吸附²³⁹Pu的特性进行研究。初步的实验结果表明：固定化马尾藻生物吸附剂对²³⁹Pu的吸附平衡时间为120min;当溶液pH为2.5～5.0、²³⁹Pu溶液初始活度浓度为21.5kBq/L时,固定化马尾藻生物吸附剂对239Pu的吸附率达99.2%以上;在动态实验中,流速控制在2mL/min,重复进行5次吸附-解吸实验后,吸附率仍达98.0%以上;固定化马尾藻生物吸附剂具有较好的化学稳定性和机械强度、费用低、吸附率高和可重复使用等特点,是一种较好的²³⁹Pu生物吸附剂。     

核爆产物140Ba在大气中传输的理论分析

文章阐述核爆产物¹⁴⁰Ba在大气中传输的分析方法。从伊藤随机微分方程出发，得出解马尔可夫过程的福克 普朗克方程，证明了欧拉对流扩散方程和拉格朗日随机蒙特卡罗方法具有等价性。研究了放射性核素在大气中传输时湍流的参数化处理，包括沿水平方向和垂直方向的扩散系数、摩擦速度及Monin-Obukhof长度等。分析了²³⁹Pu裂变时各种核素衰变到¹⁴⁰Ba的衰变链及裂变产额。通过解衰变链方程，定出1ktTNT当量钚弹爆炸时产生的¹⁴⁰Ba放射性活度的时间分布源。在考虑了一个具体的地形分布和气象数据影响的情况下，计算给出了¹⁴⁰Ba在大气中放射性活度体密度随空间和时间变化的等值线图。     

钚在放射性污染区沙漠植物中的含量

研究沙漠植物中钚的含量,对于评估沙漠植物受钚污染状况,寻找钚指示和超积累植物有重要意义。本文采集某放射性污染区内的植物并分析其中²³⁹Pu的含量,获得7种沙漠植物受²³⁹Pu污染的数据,据此分析影响植物体内核素含量的因素。所研究沙漠植物体内²³⁹Pu含量平均值为(1.8±4.9)Bq/kg（干重）,明显受到钚的污染。再悬浮是造成植物表面污染严重的重要因素之一。植物体内钚的含量与植物种类、生长期、地表污染程度等密切相关。所研究沙漠植物中钚含量的大小顺序为：河西苣>芦苇>盐穗木>盐生草>黑果枸杞>刚毛柽柳>沙拐枣,其中草本植物中钚的含量均大于木本植物。     

裂变缓发γ射线能谱的蒙特卡罗模拟

采用递次衰变路径搜索和遍历的递归算法编制一程序,该程序可用于计算裂变核素在中子辐照时和辐照后任意1种或1组裂变产物在任意时刻的放射性活度、γ能谱及其随时间的变化。计算了²³⁹Pu在池式堆快中子照射下的裂变缓发γ能谱。用MCNP软件模拟了高纯锗探头对裂变缓发γ射线的能谱响应。模拟结果可用于指导核材料裂变产额测量等研究工作。     

D0→K-π+衰变过程研究

首次应用QCD因子化方法和光锥QCD求和规则系统计算D⁰→K^-π⁺衰变过程的强子矩阵元,包括领头阶因子化部分、α_s修正的硬胶子交换部分和软胶子交换部分。计算发现,在D⁰→K^-π⁺衰变过程中,软胶子交换部分贡献相当大,甚至超过领头阶因子化部分以及α_s修正的硬胶子交换部分的贡献。计算了该衰变过程的分支比,计算结果基本处在实验误差范围内。     

反符合法测量152Eu放射性溶液的活度

¹⁵²Eu的衰变纲图复杂,包括72.1%的EC衰变和27.9%的β-衰变,衰变子体退激过程中又放出140多条γ射线,其中,12条能量处在122~1408keV之间,是主要γ射线。¹⁵²Eu常用于HPGeγ谱仪能量校准和效率校准等,¹⁵²Eu的放射性活度准确测量极为重要。本工作利用4πβ(PPC)-γ(HPGe)反符合测量装置对¹⁵²Eu的活度进行绝对测量,并与4πβ-4πγ符合效率外推法和HPGeγ谱仪、4πγ高气压电离室测量的结果进行了比较。这几种方法的测量结果在不确定度范围内一致。     

气溶胶7Be活度浓度的测量方法及其应用

用三层滤膜法测定⁷Be气溶胶的过滤效率,并对测量结果进行衰变修正,得到过滤效率为85.7%。同时,分析研究杭州附近气溶胶⁷Be活度浓度的年变化规律,得出主要原因是季节性降雨。     

天然铀衰变特性

本文介绍了天然铀的辐射特性。从解衰变方程入手,计算了~(238)U与其短寿命子体达到放射平衡所需要的时间,指出了在处理天然铀污染设备中应采取特殊的方法。     

钚质量的量热法测量

量热计是核保障领域中核材料衡算非破坏性直接测量最方便和最准确的仪器之一。本工作应用一种测量钚的热功率范围为0.1～15W的量热计测量了3个²³⁸Pu含量已知的钚样品。²³⁸Pu质量测量值与参考值相对偏差均在-1.7%以内。     

α放射性比的测定方法

采用了3种α放射性比的测定方法:几何级数法、外推法和曲线拟合法。检验了几何级数法的可靠性。把外推法、曲线拟合法的结果与几何级数法的结果作了比较。     

α谱的分析方法及应用

选取了２个能准确表达用半导体α谱仪的峰形函数。推荐了一种用二重峰α谱获取峰形参数的方法，采用麦夸脱方法计算非线性参数。建立了一个多重峰α谱分析程度ＭＵＬＴ，计算了＾２４４Ｃｍ和＾２４１Ａｍ在衰变中发射的α粒子辐射几率以及钚样品中＾２４０Ｐｕ与＾２３９Ｐｕ的原子数比。并用一个标准谱检验了它的分析准确度。     

Calculation of Beta-Ray Spectra from Individual and Aggregate Fission Products

The β-ray spectra of individual fission products were calculated by using the β-decay data assuming every β-decay to be allowed transition. For the nuclides without measured decay data the β-feeding function was evaluated with the gross theory of β-decay and the β-ray spectrum was calculated from the function. The measured decay data were also supplemented with the data calculated by the gross theory for the excitation energy range above the highest measured excitation energy level. The β-ray spectra from aggregate fission products after a burst fission were calculated by using the β-ray spectrum and the atom number of each fission product nuclide and they were compared with the ones measured for thermal neutron induced fission of ²³⁵U, ²³⁹Pu and ²⁴¹Pu at Oak Ridge National Laboratory. The spectrum calculations showed excellent agreement with the measured data at shorter cooling times than 10s when many short-lived nuclides without measured decay data contributed considerably to the spectrum.     

ICP-MS测量超痕量钚时质谱干扰的消除及水中钚的测定

研究了感应耦合等离子体质谱(ICP-MS)测定超痕量钚时的质谱干扰及干扰元素的去除;建立了环境水样中超痕量钚的测定方法。方法所用的解吸液适于ICP-MS直接进样,并有效地消除铅等元素形成的多原子离子干扰。测量了溶液中的m／z238和2％HNO3空白液中的^239Pu和^242Pu计数率,对测量结果进行校正。方法的本底为20fg,方法对^239Pu的检出限为43fg,测定限为88fg。所分析的水样中,井水中的^239Pu含量低于检出限,地表水中^239Pu的含量高于检出限,湖水和河水中的^239Pu高于测定限,但属于全球沉降引起的本底,不会对公众造成辐射危害。     

人体尸解组织中钍和钚的含量及其分布的比较

本文分析测定了日本北部新■县1986和1988年死亡的33例病人的部分尸解组织(包括骨、肺、肝、脾、肾和肌肉)中~(232)Th、~(230)Th、~(228)Th 和~(239+240)Pu 的含量,并估算了组织负荷量,对钍和钚在人体内的分布进行了比较     

能谱变化对239Pu裂变室测量快中子注量的影响

热中子和共振区的中子在快中子临界装置中所占的份额很小,但是由于其相对大的截面,在慢化物存在的情况下,热中子和共振中子份额的微小变化,对^239Pu裂变室测量中子注量的结果影响很大。通过测量^239Pu裂变电离室在包镉和包硼、周围有无慢化物等情况下的反应率,Au、In活化片的镉比,S活化片在能谱变化下与^239。Pu的反应率比等,分析了快中子临界装置中热中子和共振区中子的分布,讨论了中子能谱变化对^239Pu裂变室测量快中子注量的影响及解决办法。     

人体尸解组织~(239+240)Pu含量的测定

本文用放化分离、半导体α谱仪测量的方法,分析测定了日本北部新潟县1986和1988年死亡居民尸解组织(包括骨骼)中~(239+240)Pu的含量。测定结果表明,胸骨、肝、肺、脾、肾和肌肉中~(239+240)Pu含量的均值分别为5.9、15.4、5.1、1.69、0.33和0.31mBq/kg(鲜重),其中位值分别为5.1、13.0、4.4、1.7、0.27和0.32mBq/kg(鲜重)。     

Decay Heat Calculations Based on Theoretical Estimation of Average Beta- and Gamma-Energies Released from Short-Lived Fission Products

Fission product decay heat of ²³⁵U was calculated for short cooling-time on the basis of a preliminary version of a new decay data library recently completed by the Japanese Nuclear Data Committee. It was shown that a full adoption of recent publications of decay schemes to derive average energies of β- and γ-rays, ē_β, and ē_γ, leads to a large underestimation of the γ-ray component of the decay heat and to an overestimation of the β-ray component. In order to remedy this, theoretical values of ē_β and ē_γ were introduced for high Q-value decays, which were obtained with a gross theory of β-decay. It improved remarkably the agreement between calculation and experiment not only for the ²³⁵U decay heat but for ²³⁹Pu and ²⁴¹Pu as well. It was concluded that a large part of decay schemes recently published for high Q-value nuclides are inappropriate to use in calculations of ē_β and ē_γ, because they fail to reproduce the effect of β- strengths at high excitations, which makes ē_β small and ē_γ large. The use of the gross theory introduces this effect correctly into the values of ē_β and ē_γ and, hence, leads to a quite good prediction of both β- and γ-ray components of the decay heat.     

Validation of decay heat calculation results of ORIGEN2.2 and CASMO5 for light water reactor fuel

Comparing with the fission product nuclide (FP) decay heat summation calculation result in MeV/sec/fission based on the JENDL FP decay and yield data files 2011 for the burst fission, FP decay heat calculated by ORIGEN2.2 coupled with JENDL-4.0 base library ORLIBJ40 was verified at the cooling time from 1 sec to 10⁸ sec for ²³⁵U (thermal), ²³⁸U (fast), ²³⁹Pu (thermal) and ²⁴¹Pu (thermal). For these fission nuclides, FP decay heat calculated by CASMO5 at the same cooling time after a short irradiation (10⁴ sec) was also compared with that of ORIGEN2.2. In the analysis of decay heat measurements at the cooling time from 2.3 years to 27 years consisting of four data sets on the fuel assemblies discharged from the US PWRs and BWRs, and the Swedish PWRs and BWRs, the average values of the ratios of the calculated to measured results (C/E's) were from 0.972 to 1.031 for ORIGEN2.2, and from 0.977 to 1.016 for CASMO5. The standard deviations of C/E's for the four data sets were from 0.02 to 0.03 for the both codes except for those of the US BWR fuel assemblies which were from 0.11 to 0.12. The obtained C/E's were similar to those in the precedent study.     

铀钚中子裂变质量分布半经验公式的参数

一、引言对于铀钚中子裂变质量链产额随入射中子能量的变化,已积累了一些数据,Moriyama和Ohnishi(以下简称MO)提出了一个系统学公式,但是对铀钚同位素误差较大。Cook等人做了类似的工作,也还有值得改进的地方。本文用他们的公式拟合了~(235)U,~(238)U和~(239)Pu的实验编评数据,给出了新的参数,精确度有所提高,为进一步的改进提供了基础。