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活性炭除碘性能检验的试验装置研制 总被引:1,自引:1,他引:0
用于核设施空气净化系统的活性炭必须在规定条件下进行除碘性能的检验试验。为此,本实验室参照美国 ASTM D3803—1980“核级气相吸附剂除碘性能检验的标准试验方法”的要求,建立了核级活性炭除碘性能检验的试验装置。该装置采用常压和高压两套系统进行五种条件下的核级活性炭除碘性能的检验试验。调试试验结果表明,常压系统的气流参数易于控制,试验数据的重复性好;高压系统气流参数的控制可基本达到美国标准试验方法的要求。 相似文献
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本文主要介绍了DQ 2型气载放射性碘采样器的结构特点和技术性能的测试结果。粒子碘单元采用直径 60mm的高效过滤膜 ,气态碘单元采用 2级以粒径 60~ 80目、厚度为 2cm的浸渍椰壳活性炭为吸附剂的活性炭盒采样。测试结果表明 :1 )气密性好 ,气态碘单元未见可检出的泄漏 ,粒子碘单元的泄漏率小于 0 .1 % ;2 )阻力较小 ,在 8.0m3/h的流量下 ,采样器的总阻力为 3 0kPa;3 )效率高 ,对粒子碘的采样效率可达 99.9% ,甲基碘的吸附效率随采样流量和相对湿度的增加而下降 ,当流量为 3 .0m3/h,相对湿度低于 40 % ,炭层厚度为 2cm时 ,对甲基碘的吸附效率达到 99.997% ,可用于碘吸附器的除碘效率试验 ;4)采样器在 80℃下仍可使用 ;在高相对湿度 (95 % )时 ,推荐的采样流量为不超过 3m3/h。 相似文献
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采用非剧毒三甲基氯硅烷/碘化钠作为去烷基化试剂与磷酰基乙酸三甲酯反应,代替剧毒品硫酸二甲酯制备用于碘吸附器检验的气态放射性甲基碘。分别在实验室碘吸附器整机检验装置和核电站通风净化系统中,采用替代方法与"硫酸二甲酯法"进行了碘吸附器净化系数测定的对比试验,同时试验观察了替代试剂对甲基碘发生器有机材料部件的影响。试验结果表明,采用替代方法与"硫酸二甲酯法"测得的碘吸附器净化系数基本一致,所用替代试剂与试验装置相容性较好,初步判定可用于碘吸附器整机检验和核电站碘吸附器现场试验,具有广阔的应用前景。 相似文献
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本文主要介绍了DQ-2型气载放射性碘采样器的结构特点和技术性能的测试结果。粒子碘单元采用直径60mm的高效过滤膜,气态碘单元采用2级以粒径60-80目,厚度为2cm的浸渍椰 壳活性炭为吸附剂的活性炭盒采样。结果表明:1)气密性好,气态碘单元未见可检出的泄漏,粒子碘单元的泄漏率小于0.1%;2)阻力较小,在8.0m^3/h的流量下,采样器的总阻力为30kPa;3)效率高,对粒子碘的采样效率可达99.9%,甲基碘的吸附效率随采样流量和相对湿度的增加而下降,当流量为3.0m^3/h,相对湿度低于40%,炭层厚度为2cm时,对甲基碘的吸附效率达到99.997%,可用于碘吸附器的除碘效率试验;4)采样器在80℃下仍可使用;在高相对湿度(95%)时,推荐的采样流量为不超过3m^3/h。 相似文献
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对环己烷气体在碘吸附器用浸渍活性炭上的动态解吸行为进行了实验研究。考察了不同的载气温度、相对湿度、流速、炭床厚度以及进气中环己烷浓度对环己烷在活性炭床上解吸行为的影响,为环己烷试验方法在碘吸附器现场泄漏率试验的研究及推广提供了一定的理论支撑。试验结果表明:(1)在40 ℃,30%相对湿度条件下环己烷在活性炭床上可滞留约500 min,增大气流温度、湿度、浓度和载气流速可以减少滞留时间,其中温度对滞留时间的影响最为显著。(2)在气流相对湿度为80%时,浓度为100 ppm(10-6)的环己烷在活性炭床上的滞留时间仍达到90 min,这有利于高湿度条件下进行碘吸附器泄漏率试验。 相似文献
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本文报道了一种用于核设施周围环境和工作场所气载放射性碘监测的 DQ—01型碘取样器的性能试验结果。试验测定了采样流量、相对湿度及温度等因素对该取样器捕集放射性碘的效率的影响。试验结果表明,在环境温度和相对湿度小于95%下,即使取样流速高达1061 cm/s,床深6 cm 的取样器对甲基碘的捕集效率也大于95%。 相似文献
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Sandia National Laboratories completed the testing of a 1:6-scale containment building for a light water reactor in July 1987. Results from this and other containment model testing are being used by the US Nuclear Regulatory Commission to benchmark analytical techniques. The validated techniques can then be used to predict the behavior of actual nuclear power plant containments to a variety of hypothesized severe accidents.The most recent containment building tested was made of reinforced concrete and had many of the features found in full-size containments. Testing consistent of a structural integrity test, and integrated leak rate test, and concluded with an overpressurization test of the structure. Highlights of the results from the overpressurization of the containment model are presented. 相似文献
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As part of the U.S. Nuclear Regulatory Commission's (USNRC) Containment Integrity Program, a full-size personnel airlock for a nuclear containment building was subjected to conditions simulating a severe accident.The objective of the test was to characterize the performance of an airlock when subjected to conditions that exceeded design. The gasket tested was a “double dog-ear” configuration made from an elastomer known as EPDM E603. The data obtained from this test will be used by SNL as a benchmark for development of analytical methods.Strain, temperature, displacements, pressure, and leak rate data were measured and recorded from over 330 transducers. The test lasted approximately 60 hours. Data were recorded at regular intervals during heating, pressurization and depressurization.The airlock was originally designed for 340°F and 60 psig. The airlock inner door and bulkhead were exposed to a maximum air temperature of approximately 850°F and a maximum air pressure of 300 psig. Two heating and pressurization cycles were planned; one to heat the air to 400°F and pressurize to 300 psig, and the second to heat to 800°F and pressurize to 300 psig. No significant leakage was recorded during these two cycles. A third cycle was added to the test program. The air temperature was increased to approximately 850°F and held at this temperature for nearly 12 hours. Pressure was increased and the inner door seal failed at a pressure of 150.5 psig. The maximum leak rate recorded past the inner door seal was 706 SCFM. The outer door seal did not fail. 相似文献
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《Fusion Engineering and Design》2014,89(12):3117-3124
In this study, a new explosive welding method provided an effective way for manufacturing ITER-grade 316L(N)/CuCrZr hollow structural member. The welding parameters (stand-off distance and explosion rate) were calculated respectively using equivalent frontal collision wave model and effective energy model. The welded samples were subject to two step heat treatment cycles (solution annealing and aging). Optical microscopy (OM) and scanning electron microscopy (SEM) were utilized to analyze the microstructure of bonding interface. The mechanical properties of the welded samples were evaluated through microhardness test and tensile test. Moreover, the sealing property of the welded specimens was measured through helium leak test.Microstructural analysis showed that the welded sample using effective energy model had an ideal wavy interface. The results of microhardness test revealed an increase in hardness for both sides near to the bonding interface. And the hardening phenomenon of interface region disappeared after the solution annealing. SEM observation indicated that the samples with the post heat treatments exhibited a ductile fracture with dimple features after tensile test. After the specimens undergo aging strengthening, there was an obvious increase in the strength for all specimens. The helium leak test results have proven that the welded specimens are soundness. 相似文献
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研究了硫酸二甲酯法、三甲基氯硅烷-磷酰基乙酸三甲酯法和同位素交换法在碘吸附器性能试验及核通风系统除碘效率试验中应用的优缺点。对三种方法的试验产率、试剂及残液毒性、试验可靠性及设备稳定性等方面进行了综合研究。研究结果表明:硫酸二甲酯法由于试剂毒性而在应用上受到一定限制;三甲基氯硅烷-磷酰基乙酸三甲酯法作为低毒性试验方法总体满足现场试验要求,但由于该方法所用试剂对试验设备会造成一定侵蚀,因此需要作一些改进;同位素交换法作为一种新颖的试验方法具有毒性低、产率高、操控简单稳定、风险较低等优点,推荐使用。 相似文献