低环径比聚变托卡马克液态金属包铜中心导体柱

低环径比(LAR)聚变托卡马克可作为一种紧凑中子源,为聚变早期利用提供了有效途径。本文针对其关键部件中心导体提出新颖液态金属(LM)包钢中心导体往设计结构,其结构由既可增殖氚又可降低导体辐照损伤的防护层和负载巨大电流(>10MA)的中心导体区组成。与常规中心导体柱(CCP)相比,其优势在于:防护区减小了铜导体的辐照损伤;提高了中子利用率及氚增殖率;优化结构的铜导体,保证了较低的欧姆损耗。     

~(235)U的有效“俘获/裂变”截面比(α_5)和堆元件燃耗[Bu(%)]的一种计算方法

一、引言~(235)U的有效“俘获/裂变”截面比(α_5)对测定反应堆元件的燃耗B_u(%)、研究反应堆的特性和运行状况都是很重要的参数。在一定燃耗深度但仍属浅燃耗范围内,α_5值变化较小,还可以通过测定反应堆元件辐照前和辐照后~(235)U和~(236)U的含量来确定它的数值,常采用的α_5值     

LDR辐射后脾细胞裂解成分对淋巴细胞NK活性的影响

研究了低剂量辐射(LDR)后脾细胞裂解成分对淋巴细胞自然杀伤细胞(NK)活性的影响。用McAb直接法分离出CD57细胞和非CD57细胞(除CD57外的所有淋巴细胞)并以两者为效应细胞，K562细胞为靶细胞，将CD57与非CD57杀伤肿瘤细胞的作用进行比较；测定计算各自的杀伤活性并观察LDR辐射后脾细胞裂解成分对杀伤活性的影响。结果表明，CD57及非CD57细胞均对肿瘤细胞有杀伤作用，且非CD57细胞的作用更强；LDR辐射后脾细胞裂解成分能分别增强CD57及非CD57细胞体外抗肿瘤细胞效应(NK细胞活性及NK活性)。     

淋巴因子相应靶细胞的小剂量辐射效应

观察了单次小剂量Ｘ射线全身照射后Ｃ５７ＢＬ／６小鼠胸腺细胞ＩＬ－１反应性和脾细胞ＩＬ－２反应性的变化，发现在１００ｍＧｙ以内的小剂量照射后，整个胸腺和脾脏的细胞数趋于增多，胸腺细胞对ＩＬ－１的反应性和脾细胞对ＩＬ－２的反应性趋于增强，体外照ＩＬ－２细胞亦出现同样的反应趋势，但统计学处理与对照组比较均地明显差异。     

Mass flow rate sensitivity and uncertainty analysis in natural circulation boiling water reactor core from Monte Carlo simulations

Our aim was to evaluate the sensitivity and uncertainty of mass flow rate in the core on the performance of natural circulation boiling water reactor (NCBWR). This analysis was carried out through Monte Carlo simulations of sizes up to 40,000, and the size, i.e., repetition of 25,000 was considered as valid for routine applications. A simplified boiling water reactor (SBWR) was used as an application example of Monte Carlo method. The numerical code to simulate the SBWR performance considers a one-dimensional thermo-hydraulics model along with non-equilibrium thermodynamics and non-homogeneous flow approximation, one-dimensional fuel rod heat transfer. The neutron processes were simulated with a point reactor kinetics model with six groups of delayed neutrons. The sensitivity was evaluated in terms of 99% confidence intervals of the mean to understand the range of mean values that may represent the entire statistical population of performance variables. The regression analysis with mass flow rate as the predictor variable showed statistically valid linear correlations for both neutron flux and fuel temperature and quadratic relationship for the void fraction. No statistically valid correlation was observed for the total heat flux as a function of the mass flow rate although heat flux at individual nodes was positively correlated with this variable. These correlations are useful for the study, analysis and design of any NCBWR. The uncertainties were propagated as follows: for 10% change in the mass flow rate in the core, the responses for neutron power, total heat flux, average fuel temperature and average void fraction changed by 8.74%, 7.77%, 2.74% and 0.58%, respectively.