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51.
Material Disposal Area G is the primary low-levelradioactive waste disposal site at Los Alamos NationalLaboratory, New Mexico, and is adjacent to Pueblo of SanIldefonso lands. Pueblo residents and Los Alamos scientists areconcerned about radiological doses resulting from uptake of AreaG radionuclides by mule deer (Odocoileus hemionus) andRocky Mountain elk (Cervus elaphus), then consumption ofdeer and elk meat by humans. Tissue samples were collected fromdeer and elk accidentally killed near Area G and were analyzedfor 3H, 90Sr, total U, 238Pu, 239, 240Pu,241Am, and 137Cs. These data were used to estimatehuman doses based on meat consumption of 23 kg y-1. Humandoses were also modeled using RESRAD, and dose rates to deer andelk were estimated with a screening model. Dose estimates tohumans from tissue consumption were 2.9 × 10-3 mSv y-1and 1.6 × 10-3 mSv y-1 from deer and elk, respectively,and RESRAD dose estimates were of the same order of magnitude. Estimated dose rates to deer and elk were 2.1 × 10-4 mGyd-1 and 4.7 × 10-4 mGy d-1, respectively. Allestimated doses were significantly less than established exposurelimits or guidelines. 相似文献
52.
用国产ETLD-80型热释光环境剂量计调查了哈密地区环境天然贯穿辐射水平.结果表明,哈密地区室外、室内宇宙射线电离辐射空气吸收剂量率分别为(3.7±0.3 )、(3.3±0.3)×10~(-8)Gy/h,人口加权平均值分别为3.2和2.8×10~(-8)Gy/h.地球γ辐射空气吸收剂量率分别为(5.8±0.9)、(7.7±1.2)×10~(-8)Gy/h,人口加权平均值分别为5.0和6.6×10~(-8)Gy/h.天然贯穿辐射所致居民有效剂量当量为71.7μSv/a(宇宙辐射298μSv/a,地球γ辐射419μSv/a). 相似文献
53.
An estimation of the indoor background radiation dose distribution was carried out in dwellings of eleven villages located within and around the uranium mineralization area of Kylleng-Pyndensohiong, Mawthabah in West Khasi Hills District of Meghalaya, India. The ambient indoor gamma radiation level was monitored using Thermo Luminescence Dosimeters (TLDs) while the indoor radon and thoron concentration was measured using twin-cup dosimeters employing Solid State Nuclear Track Detectors (SSNTDs). Results obtained from the study reveals that the local inhabitants of villages located close to the mining site receive higher doses than those inhabitants of villages located at a much farther distance from the mining site. The average total annual effective dose was found to be varying from 1.2 mSv y−1 in the village of Langpa to 3.4 mSv y−1 in the village of Nongbah Jynrin. The data obtained will serve as a reference in documenting changes to environmental radioactivity if mining is to be carried out in the future. 相似文献
54.
Some important naturally occurring α- and β-radionuclides in drinking water samples collected in Italy were determined and the radiological quality evaluated. The mean activity concentrations (mBq L−1) of the radionuclides in the water samples were almost in the order: 26 ± 36 (234U) > 21 ± 30 (238U) > 8.9 ± 15 (226Ra) > 4.8 ± 6.3 (228Ra) > 4.0 ± 4.1 (210Pb) > 3.2 ± 3.7 (210Po) > 2.7 ± 1.2 (212Pb) > 1.4 ± 1.8 (224Ra) > 1.1 ± 1.3 (235U) > 0.26 ± 0.39 (228Th) > 0.0023 ± 0.0009 (230Th) > 0.0013 ± 0.0006 (232Th). The mean estimated dose (μSv yr−1) to an adult from the water intake was in this order: 2.8 ± 3.3 (210Po) > 2.4 ± 3.2 (228Ra) > 2.1 ± 2.1 (210Pb) > 1.8 ± 3.1 (226Ra) > 0.94 ± 1.30 (234U) > 0.70 ± 0.98 (238U) > 0.069 ± 0.087 (224Ra) > 0.036 ± 0.044 (235U) > 0.014 ± 0.021 (228Th) > 0.012 ± 0.005 (212Pb) > 0.00035 ± 0.00029 (230Th) > 0.00022 ± 0.00009 (232Th). It is obvious that 210Po, 228Ra, 210Pb and 226Ra are the most important dose contributors in the drinking water intake. As far as the seventeen brands of analysed drinking water were concerned, the committed effective doses were in the range of 2.81–38.5 μSv yr−1, all well below the reference level of the committed effective dose (100 μSv yr−1) recommended by the WHO. These data throw some light on the scale of the radiological impact on the public from some naturally occurring radionuclides in drinking water, and can also serve as a comparison for the dose contribution from artificial radionuclides released to the environment as a result of human practices. Based on the radionuclide composition in the analysed waters, comment was made on the new screening level for gross α activity in guidelines for drinking-water quality recommended by the WHO, 2004. 相似文献
55.
某铀矿山废石场及尾砂库氡污染调查 总被引:5,自引:0,他引:5
黄建兵 《环境监测管理与技术》2001,13(2):27-30
通过对某退役铀矿山的 14个废石堆放场及 3个尾砂库氡析出率的测量及内照射剂量的估算 ,表明 ,只有一个废石场的氡析出率超过国家规定的管理限值水平 ;尾砂库的氡析出率较高 ,个别测点的氡析出率超出管理限值水平近 7倍 ;因氡析出而使当地居民额外所受的年最大有效剂量当量为 0 0 5 8mSv。指出在尾砂库表面覆盖黄土 ,可以有效降低氡析出水平 ,当覆盖厚度达 0 5m时 ,可将氡析出水平降低 84%以上。 相似文献
56.
氚靶制备现场氚的辐射防护 总被引:2,自引:0,他引:2
氚靶制备过程中氚的辐射防护是整项工作能否顺利完成的关键之一,本文以一次氚靶制备为例,报道了氚靶制备现场氚的辐射防护。结果表明:在氚靶制备过程中,充氚手套箱、操作间和排放烟囱内的氚浓度均未达到操作现场设定的氚的管理值,本次制靶过程中外排氚量为6.78×10^9Bq;制靶期间操作间地面和工作台、仪表上氚表面污染最大值分别为23.20Bq/cm^2、1.85Bq/cm^2、11.53Bq/cm^2,均远低于GB18871—2002中规定的控制区表面放射性物质污染控制水平值;剂量监测间地面氚表面污染最大值为8.92Bq/cm^2,低于国家标准中对监督区表面氚污染的控制限值;操作人员休息间、剂量监测控制间和走廊地面氚表面污染最大值分别为15.28Bq/cm^2、3.35Bq/cm^2、14.05Bq/cm^2,低于国标中对非限制区表面氚污染的控制水平;本次充氚活动中现场工作人员所受的剂量在国家标准值以下,对公众造成的附加剂量远低于GB18871—2002中规定的限值。 相似文献
57.
58.
氡及其衰变子体会对人体产生辐射损伤。高浓度的氡可以致癌,而其具有无色、无嗅及无味的特性,因此难以察觉。据国内外的最新研究结果表明,氡是仅次于吸烟诱发肺病而死亡的第二大病因。对乌鲁木齐市有代表性的商场超市、酒店、娱乐场所以及宾馆的室内氡浓度进行监测,室内氡浓度平均值23.8Bq/m3,低于国标的400Bq/m3;并估算出对其内工作人员所造成的年有效剂量为0.137mSy,低于世界平均值1.008mSy,对于只作短暂停留的客人来说,所受到的剂量还要低。 相似文献
59.
采用固体核径迹法和热释光剂量计,对成都市不同建造年代、建筑类型、建筑结构、建筑材料以及楼层的100间居室进行了室内环境氡浓度和辐射水平的测量.调查结果表明:成都市居室环境中氡浓度范围为(8.4~177.1)Bq/m3,算术平均值为(39.5±22.9)Bq/m3,低于世界平均水平;辐射水平的范围为(74.7~164.7)nSv/h,算术平均值为(122.0±16.2)nSv/h,与室内氡浓度无相关性.不同建筑年代、建筑类型、建筑楼层和建筑材料的房屋室内环境氡浓度水平有显著差异.室内环境氡及其子体和辐射照射所致公众的平均年有效剂量分别为0.99mSv和0.85mSv. 相似文献
60.
为调查南京市学校教室内空气微生物污染状况,本研究各选一所幼儿园、小学、初中和大学,每所学校分别随机选取10间教室,采用六级安德森采样器进行空气微生物采样.研究发现,在南京地区所调研的这4所不同类型的学校中,幼儿园室内空气微生物浓度最高,细菌和真菌浓度均值分别为605CFU/m3和648CFU/m3,均显著高于其余3所学校.室内细菌和真菌粒径分布趋同,峰值均出现在Ⅴ级(1.1~2.1μm).仅在大学教室内,发现环境参数与空气微生物浓度存在显著相关性.幼儿园教室内学生每天吸入的细菌和真菌剂量分别为150.2CFU/kg和160.9CFU/kg,均显著高于其他学校学生. 相似文献