共查询到20条相似文献,搜索用时 60 毫秒
1.
本文通过大量的实验,对所购买的Carbolite生物氚碳燃烧装置进行了局部改良,优化了环境生物有机氚分析方法的设置条件。优化后,样品的生成水回收率可达到80%以上,Carbolite生物氚碳燃烧装置氧化燃烧更充分,制样过程更安全;相同环境样品不同实验人员的测量结果相对偏差小于30%。结果表明,本文的分析方法具有重现性。 相似文献
2.
3.
燃烧制样法测定牛奶中的氚 总被引:1,自引:0,他引:1
本文用燃烧法研究了牛奶中氚的测量方法,使用自制的简单石英燃烧装置和HR-1型蜂窝状燃烧催化剂。用低本底液体闪烁仪进行测量。以水和氚放射性回收率验证该燃烧器的性能。牛奶中水回收率为98.6±1.5%。氚水和有机氚的回收率相一致,都在97%左右。 相似文献
4.
5.
6.
7.
从核设施释放到大气中的氚主要以氚化水(HTO)和氚化氢(HT)两种形式存在,最终以HTO的形式进入植物体。植物体中的氚有两种化学形态:自由水氚(TFWT)和有机氚(OBT),其中OBT又被细分为交换性OBT和非交换性OBT。与TFWT相比,OBT在植物体内有较长的滞留时间和较大的剂量转换因子,在氚的食入剂量中OBT占主要份额,因此有必要对植物中的OBT展开全面研究。本文就植物中OBT的定义、交换性OBT和非交换性OBT的确定、OBT的形成过程及其影响因子、OBT预测模型的研究进行综述,同时对今后植物中OBT应重点研究的内容进行了简单分析,以期为植物中OBT的研究提供一定的参考。为准确评价OBT造成的辐射剂量,今后对OBT的研究中应着重从测量、夜间形成机理和环境中的行为等方面进行。 相似文献
8.
9.
中国原子能科学研究院有机废液焚烧装置于1986年建成,并于1989年8—9月焚烧处理了1.7 t 含氚(10~8Bq/L)废机油。监测结果表明,这次焚烧排放造成的空气中氚浓度最高值为13.3Bq/m~3,估算结果与监测结果相一致;对周围居民产生的最大个人年有效剂量当量为0.32 μSv。 相似文献
10.
11.
12.
被动式氚取样器性能的实验研究 总被引:1,自引:0,他引:1
介绍了核设施工作场所和环境空气中氚化水蒸气HTO的监测,被动式氚取样器在国外已经得到非常广泛的应用,所研制的被动式氚取样器,特别适用于7-30d的长期取样,给出该取样周期内空气中HTO浓度的平均值。 相似文献
13.
对土壤-植物系统中氚迁移研究的意义、国内外研究进展作了概括性的介绍与展望,包括氚在不同土壤和植物中的时空分布、迁移规律及其影响因素、氚的化学形态和氚迁移数学模型研究等。总结了已取得的研究成果,并分析、讨论了研究中存在的问题。 相似文献
14.
《核技术(英文版)》2023,34(7):165-177
China Fusion Engineering Test Reactor(CFETR)is China's self-designed and ongoing next-generation fusion reactor project.Tritium confinement systems in CFETR guarantee that the radiation level remains below the safety limit during tritium handling and operation in the fuel cycle system.Our tritium technology team is responsible for studying tritium transport behavior in the CFETR tritium safety confinement systems of the National Key R&D Program of China launched in 2017,and we are conducting CFETR tritium plant safety analysis by using CFD software.In this paper,the tritium migration and removal behavior were studied under a postulated accident condition for the Tokamak Exhaust Processing system of CFETR.The quantitative results of the transport behavior of tritium in the process room and glove box during the whole accident sequence(e.g.,tritium release,alarm,isolation,and tritium removal)have been presented.The results support the detailed design and engineering demonstration-related research of CFETR tritium plant. 相似文献
15.
On-site groundwater has been reported to be contaminated by the unplanned release of liquid radioactive material at some nuclear power plants. Thus, it is of utmost importance to implement a timely and effective groundwater protection program at a site based on a good understanding of groundwater flow and a reasonable prediction for the potential impact of the unplanned release. In this study, the tritium migration has been simulated based on the modeling result of groundwater at Wolsong Plant 1 site to assess the potential impact of an unplanned release in the form of a leak. The results indicate that the groundwater eventually flowed into the sea, leaving marine activities as the only possible exposure pathway for receptors. Furthermore, the tritium concentrations in groundwater were simulated to be lowered very quickly with groundwater approaching the sea. Therefore, an additional radiation dose contribution due to the discharge of the contaminated groundwater was estimated to be negligible. Particularly, the draining effect of the dewatering sumps was shown to have a strong influence on the groundwater flow characteristics and the simulation of tritium migration, mainly decreasing the spread rate of the contaminated groundwater, which is advantageous to the protection of groundwater. 相似文献
16.
Tritium behavior in the reactor such as production, diffusion and release are accompanied by their adsorption and desorption in graphite materials, which are essential to the safety of high temperature gas cooled reactor (HTGR). In order to study this important issue, hydrogen instead of tritium is experimentally used in this work and justified viable by theory. By performing multiple sets of comparative experiments, the features of hydrogen adsorption and desorption behavior changing by adsorption temperature and time in typical graphites used in HTR-PM (High Temperature Gas Cooled Reactor – Pebble Bed Module), i.e. reflective layer, fuel element and boron carbon bricks, have been observed and analyzed. Furthermore, the adsorption rates of hydrogen in the three materials as above at different conditions are also given. Based on the experimental results, tritium behavior in the HTR-PM was inferred and estimated, which is significant for the further study on the mechanism of tritium transport. 相似文献
17.
18.
There is an increasing requirement for tritium to supply the fuel needs of current experimental fusion devices and in the initial startup of future power generating reactors. Tritium is produced in heavy water reactors through deuterium activation, but the total production capacity of Canadian operated CANDUs will fall short of future demands, during the period before and for some time after self-sufficient reactors become available. Consequently, methods of enhancing tritium generating rates warrant investigation. Herein we provide the results of an inquiry into the feasibility of enhancing tritium production levels through the activation of helium-3 following its external addition to the heavy water moderator system of a hypothetical 500–600 MWe CANDU reactor. The approach adopted involves simulation of the temporal evolution of the tritium activities, originating from2H(n,)3H and3He(n, p)3H, as described by a simple first order kinetic model. The results suggest that the frequent addition of helium-3 to the moderator water will enhance tritium production inventories. The enhancement factor is highly dependent upon the rate at which helium-3 irretrievably escapes to the moderator cover gas. However, the direct activation of helium-3, contained in a closed loop such as the annulus gas system, for example, would be essentially complete within a few weeks without any significant loss. 相似文献
19.