稀土尾矿砂放射性活度的测量与计算分析

准确测量并计算稀土尾矿砂的放射性活度浓度及其变化规律对制定相应的豁免标准和日后的处理处置具有重要的意义。根据选取的特征 射线,分析对比平衡与非平衡状态下铀系、钍系、锕系三个天然衰变系的总活度浓度,结合衰变链的一般动力学方程,计算总放射性活度与每个核素的放射性活度,并研究钍系各核素在平衡被不同程度破坏的情况下随时间的变化规律。结果显示,按照非平衡情况下计算得出的总α 和总β 放射性活度浓度比平衡情况下的更接近实际测量结果,此外,钍系核素在平衡被破坏后的放射性活度随时间变化情况与母体和228Ra 的初始放射性活度浓度有关,若228Ra 小于232Th,则总放射性活度在60 a再次平衡后达到最大值,为10 倍的母体活度;若228Ra 大于232Th,则总放射性活度在3.82 a 出现最大值,为4.57 倍母体活度与5.25 倍第一子体228Ra 的初始活度浓度之和。因此,可知稀土尾矿砂放射性活度已经遭到破坏,其总活度浓度应该采用非平衡情况下的几个特征核素的活度浓度共同计算得到,并且需计算分析其随时间变化出现的最大值,以此来确定是否超过相关法规标准。It is of great significance to measure and calculate rare earth tailing radioactivity for the development of appropriate standards and exemption disposal. The total activity concentration of the three natural decay series (uranium series, thorium series, actinium series) was analyzed under the equilibrium and disequilibrium state according to the selected characteristic  γ-rays. At the same time, we calculated the total activity concentration and the radioactivity for each radionuclide based on the general kinetic equations of decay chain and studied the trend of each radionuclide of thorium-series under different degrees of disequilibrium with time. The results demonstrated that the total radioactivity of and calculated in disequilibrium state was more closed to the actual measurement results compared to that in equilibrium state. In addition, the activity changes with time of thorium series in disequilibrium state are related to the initial activity concentration of the mother nuclide and 228Ra. If the activity concentration of 228Ra is less than that of 232Th, the total activity peak will be 10 times to maternal activity and appear after 60 a when the thorium series become balance again. If the activity concentration of 228Ra is greater than that of 232Th, the maximum total activity will appear in 3.82 a, and will be the sum of 4.57 times of the initial activity concentration of the mother nuclide and 5.25 times of the initial activity concentration of the first daughter 228Ra. Therefore, the rare earth tailings have been in disequilibrium state, and its total activity concentration should be determined based on the activity concentration of several  feature radionuclides. In addition, the maximum value of the activity concentration is profitable to judge whether the activity concentration is fit with relevant regulations and standards.     

反应堆235U裂变源辐射防护材料的优化设计

以热中子反应堆²³⁵U裂变源为辐射源,利用MCNP程序对其能谱进行模拟并研究其辐射防护,结果表明对²³⁵U裂变源所发射的能量高于3MeV的瞬发中子,重金属具有良好的屏蔽效果,而对于能量低于1MeV的中子,轻氢材料的防护效果更好;W/LiH,W/B₄C,TiH₂/W三种复合材料当质量比满足：W：LiH=19：1,W：B₄C=9：1,W：TiH₂=3：1时材料的屏蔽效果最佳;通过遗传算法结合MCNP模拟,得到W/TiH₂/B₄C,TiH₂/Cu/Gd,TiH₂/B₄C/Gd三种复合材料的最优组分配比,源每次裂变产生的粒子穿过这三种材料后在等效组织中造成的剂量当量率（10^-11Sv·h^-1）与材料厚度呈指数下降关系,三种材料分别可近似为1.071exp（-0.187 8x）,1.077exp（-0.166 2x）和1.608exp（-0.171 9x）,x为材料厚度（cm）.