Analytical Models for Migration of Radionuclides in Geologic Sorbing Media

In safety evaluation of nuclear waste repository systems, the analysis on migration of radionuclides in geologic media is important. In previous analytical models called Band- Release, Step-Release and Impulse-Release for decay chains, nuclide-specific release rate and time-dependence of release rate can not be taken into consideration. In this paper, two new release models are proposed. In Preferential-Release model, both of nuclide-specific release rate and time-dependence of leach are taken into account. Exponential-Release model is a special case of Preferential-Release model, in which no preferentiality in leach is assumed. The obtained analytical solutions for these new models are applicable even to four or more member decay chains and are as simple as those for the previous models.

As an example of the application of the new models, the discharge rates of the four nuclides in the decay chain of ²³⁸Pu→²³⁴U→ ²³⁰Th→²³⁶Ra→ into a surface water body are calculated as a function of time after the start of leach and path length from the repository. By using the result, heavy hazard due to ²³⁸Pu at short distance and ²²⁶Ra at long distance are also discussed briefly.     

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.     

基于修正的卡尔曼滤波自适应跟踪算法

针对卡尔曼滤波对匀速运动目标能有效的跟踪,但是当目标出现转弯时,很难达到跟踪精度的要求,甚至丢失目标的现象.对卡尔曼滤波算法进行了改进,在观测向量中引入了两个加速度误差变量,它们动态地修正状态估计误差从而减少跟踪精度误差,形成了修正的Kalman算法.但是由于状态变量维数增加,使得计算量增加,实时性下降,将卡尔曼滤波算法与修正的卡尔曼滤波算法两种算法相结合,提出了基于修正的卡尔曼滤波自适应跟踪算法.仿真结果表明,具有良好的稳定性和精确度,优于一般的卡尔曼滤波算法.     

The SPL1 tRNA splicing gene of Candida maltosa and Candida albicans

The tRNA splicing gene SPL1-1 has been cloned and sequenced in Saccharomyces cerevisiae (Kolman and Soll, 1993). Sequence adjacent to the LEU2 gene in Candida maltosa showed some homology to the SPL1-1 gene of S. cerevisiae. This work describes the sequencing of the SPL1 tRNA splicing genes from C. maltosa and C. albicans and the analysis of these genes. Comparison of these sequences and the relationship observed between the LEU2 and SPL1 genes in these yeasts suggests that there may be some synteny amongst various species of yeasts. The coding region of the C. maltosa SPL1 region described in this work differs from previously described partial sequences in that it is a complete uninterrupted open reading frame. Two strains of C. maltosa were each shown to contain different alleles, one uninterrupted open reading frame and one disrupted open reading frame. The sequences have been deposited in the GenBank/EMBL data libraries under Accession Numbers X72940, AF000115, AF000116, AF000117, AF000118, AF000119 and AF000120. © 1998 John Wiley & Sons, Ltd.     

短寿命核素气溶胶监测相关问题探讨

目前的放射性气溶胶连续监测仪或连续空气监测仪,都是针对长寿命的α放射性核素(如U,Pu)或β放射性核素(如¹³⁷Cs,⁹⁰Sr),因而在采样测量过程中都不考虑被监测核素的衰变修正。但是,包括核电站在内的具有反应堆运行的核设施,对某些短寿命放射性核素(如⁸⁸Rb,¹³⁸Cs以及¹⁸F等)的气溶胶监测也是重要的。本文针对短寿命核素气溶胶监测中的有关问题进行讨论,提出了相关的可供监测仪器报告监测结果的实际可行的数据处理方法。     

AN EMPIRICAL APPROACH TO THE PREDICTION OF ELUTRIATION OF FINES FROM FLUIDIZED BEDS AT DIFFERENT FREEBOARD LEVELS

An empirical approach has been developed to predict the total entrainment flux at different levels of freeboard height. The approach is based on the results of experimental investigations carried out in a 152 mm diameter column, with FCC as the feed powder. The powder was fluidized at superficial gas velocities of 0.2 m/s and 0.7 m/s.     

秦山核电基地放射性废物最小化技术实践与探讨

介绍了秦山核电基地在放射性废物最小化方面的实践。包括建立了蒸汽发生器排污树脂和通风过滤器金属框架清洁解控工作流程;改进了水泥固化线工艺,水泥固化包装容器采用金属桶代替水泥桶;开发了废过滤器芯子暂存衰变法分类处理及一桶装多芯方案;开发了技术废物“三明治”式废物装桶和超级压实提高外包装容器效率等最小化实践。对废液、废树脂、技术废物、有机废液等处理技术进行了比较分析,建议采用废液蒸干压实技术、废树脂蒸汽重整技术、可燃废物和有机废液焚烧技术,预计秦山核电基地废物产生量可由541 m³/a减至约94 m³/a。     

La-Mg-Ni系合金循环容量衰减的机理

制备铸态及退火后La<,0.75>Mg<,0.25>Ni<,3.44>Co<,0.2>Al<,0.06>合金,以研究La-Mg-Ni系合金的循环容量衰减机理.XRD、SEM和电化学分析表明:合金的主相为(La,Mg)<,2>(Ni,Co,Al)<,7>,还有La(Ni,Co)<,5>和La(Ni,Co)<,2>相.退火...     

Maxwell-Cattaneo方程组的非标准问题的衰减界

主要研究当温度和热量流满足非标准初始条件时的Maxwell-Cattaneo方程组.通过一些微分不等式,在参数的适当的范围上,结合非标准的初始条件,证明了温度和热量流的指数衰减界可由数据项确定.同时我们也推出了一个特例的解的指数衰减界.