共查询到20条相似文献,搜索用时 125 毫秒
1.
中子管的研究进展及应用 总被引:6,自引:2,他引:4
乔亚华 《核电子学与探测技术》2008,28(6)
介绍了国内外中子管的发展及应用情况,包括其在中子测井、煤质分析、中子照相、爆炸物及毒品检测、核材料和核武器识别系统和其它领域方面的应用研究等,并展望了中子管的应用发展前景。 相似文献
2.
介绍了新近研制的多功能测井仪的原理,以及对样机的原理实验研究.仪器通过模块化设计,可以分别实现碳氧比能谱测井和中子寿命测井的功能,实现一机多用,填补了国内石油测井领域在这一方面的空白. 相似文献
3.
地层元素测井技术最新进展及其应用 总被引:2,自引:0,他引:2
地层元素测井是一种通过测量中子与地层元素原子核作用放出的伽马射线,得到元素含量进而确定矿物含量的中子伽马能谱测井技术,在复杂储层岩性识别、非常规储层评价等方面得到了广泛应用。本文简要介绍了元素能谱测井的核物理和地质基础,并对元素俘获能谱测井(ECS)、地球化学测井(GEM)和地层岩性能谱测井(FLS)等几种仪器技术指标进行分析;系统讨论了确定元素含量的谱分析技术及矿物含量的氧化物闭合模型和统计分析方法;总结了元素能谱测井在地层评价中的应用。最后提出采用可控中子源和多探测器系统、多参数测量是地层元素测井的发展趋势。 相似文献
4.
5.
采用氘-氚(D-T)可控源进行中子孔隙度测井时,其响应结果与化学源中子孔隙度测井的响应结果存在差异,使得传统化学源中子孔隙度测井的实验数据和解释模型难以适用。为了验证已有的密度校正方法是否能够用于中子孔隙度测井的结果校正,使D-T源与化学源的响应结果相接近,本文通过模拟获取不同孔隙灰岩含水地层和泥岩中的响应结果,将模拟结果与研制的实验装置测量结果进行基准检测,然后分析D-T源中子孔隙度测井校正前后与化学源中子孔隙度测井对比的响应差异,并利用实际测井数据验证可控源孔隙度测井方法的有效性。结果表明:经过密度校正后,可控源与化学源中子孔隙度的测量结果有较好的相似性,在实际测井曲线上两者也存在较好的对应关系。因此,本研究对于验证可控源中子孔隙度测井方法的有效性和今后测井仪器中放射源的可兼容替代有一定的应用意义。 相似文献
6.
7.
文章简述了脉冲中子测井方法的原理,总结了脉冲中子测井方法的分类及在石油测井中所起的作用,指出了当前脉冲中子测井存在测井数据质量不高、测井速度慢、影响因素多、解释困难、纵向分辨率低、适应性差等不足,并从硬件、软件、方法和原理四个方面阐述了脉冲中子测井的发展方向. 相似文献
8.
碳氧比能谱测井原理与实现 总被引:1,自引:0,他引:1
碳氧比能谱测井是一种新型的脉冲中子测井方法,在油田广泛推广用于评价储集层孔隙度和岩性,确定含油饱和度.本文结合在国产数控测井地面系统配接Atlas 2727碳氧比测井仪的经验,详细介绍了碳氧比的测井原理和数据传输,给出了测井方法的具体实现和应用.该方法已经在多种地面系统和测试台架得到验证,通过现场测井取得良好的应用效果. 相似文献
9.
可控源替代中子孔隙度测井中的同位素中子源已经成为石油勘探发展的必然趋势。为了提高中子孔隙度测井中可控源替代同位素中子源的兼容性与测量精度,本文针对影响地层孔隙度灵敏度的因素进行分析。首先,根据中子孔隙度响应的理论公式,推导出地层孔隙度灵敏度的响应方程,然后对其进行分析并得出影响灵敏度的各种因素。结果表明,地层中的中子减速长度对地层灵敏度变化起到主要影响作用,另外减速长度受到了源类型及能量、孔隙度、岩性、密度等因素的影响,其中中子能量和岩石密度是影响灵敏度变化的主要因素。本研究为今后可控源中子孔隙度测井的研究提供了理论依据。 相似文献
10.
11.
介绍自成靶陶瓷中子管的技术特点以及以它为核心的中子发生器的原理和特性。该中子发生器在吉林油田首次ATLAS2727C/O测井仪对接成功,并开始批量测井。 相似文献
12.
《核技术(英文版)》2016,(6):137-141
A Bonner sphere spectrometer(BSS) was developed for neutron diagnostic on HL_2A Tokamak.It contains eight polyethylene spheres embedded with SP9~3 He proportional counter.Before setting up on the Tokamak experimental hall,a verification experiment was arranged on a~(241)Am–Be neutron source to test its spectrometry capability.The neutron response functions were calculated by Monte Carlo code Geant4 to simulate the real measurement environments.By least square method,the neutron spectrum was finally unfolded on log domain from0.1 e V to 11 Me V.It has a remarkable consistency to the ISO 8529-1 standard~(241)Am–Be neutron spectrum.This shows that the BSS is effective and reliable for neutron spectrum determination. 相似文献
13.
E.F. Ibrahim 《Journal of Nuclear Materials》1973,46(2):169-182
Tubular specimens of Zircaloy-2, 23 mm diameter, have been creep tested in-reactor at 260 to 300°C (530 to 570 K). The specimens were biaxially stressed by internal pressure, with transverse stresses from 100 to 300 MN/m2. Zircaloy-2 was tested in three conditions; 20% cold drawn, 70% tube reduced then stress-relieved and annealed.All creep curves, both in and out of neutron fluxes, can be represented by straight lines on log strain-log time curves. Fast neutron flux increased the slopes of the log-log creep curves of the cold-worked materials. These slopes increased from 0.24–0.27 for unirradiated specimens (and specimens in the thermal neutron flux) to 0.42–0.47 for specimens in a fast neutron flux. This means that creep rate does not diminish with time as rapidly in-reactor as out-reactor. The creep behaviour of the annealed Zircaloy-2 was little affected by fast neutron flux. 相似文献
14.
《Journal of Nuclear Science and Technology》2013,50(10):416-421
A study has been made on the effect of neutron irradiation on the tensile properties at room temperature of Magnox AL80, Mg-Al alloy and unalloyed magnesium as a function of grain size. Heat treated wire specimens were encapsulated and then irradiated in the JRR-2 reactor up to exposures of 1.2x1019nvt (epi-Cd energy). As a result the parameters σ0 and k in the Petch relationship increased in magnitude after irradiations exceeding 1x1017nvt. Among the materials tested Magnox AL80 was found to be the most sensitive to neutron irradiation and unalloyed magnesium the least effected. The effect of neutron irradiation on the strain rate (ε) dependence of the tensile stress (σ) was also investigated. The effect of neutron irradiation was to increase A and to decrease B in the equation σ=A+B log ε, when σ represented the yield stresses. 相似文献
15.
在特定实验条件下的散射中子本底研究 总被引:7,自引:1,他引:6
研究了d-T中子源与探测器距离较近时,扣除实验大厅散射中子本底的方法。实验上采用屏蔽法,用了铀裂变电离室。用MCNP/4A程序和FENDL2库数据计算了实验大厅散射中子本底曲线。采用实验和计算相结合的方法扣除了在特定实验条件下的散射中子本底,方法是可行的。 相似文献
16.
17.
《Journal of Nuclear Science and Technology》2013,50(11):580-587
The slowing down of neutrons to very low energy has been examined with particular reference to cold neutron production. The neutron spectrum formed in very cold light water ice has been measured with time-of-flight technique. It is observed that at extremely low temperature the neutron temperature is much higher than the moderator temperature, whereas in the intermediate range of temperature the neutron temperature does not differ much from the moderator temperature. It is suggested that there is a limiting neutron temperature below which it does not fall, even when the moderator temperature drops further. This observation can lead to information on the nature of the mechanism for removing small amounts of energy from slow neutrons in cold solid hydrogenous moderators. By using a simplified model for the cold solid hydrogenous moderators, it is shown that low frequency lattice vibrations play an important role in producing cold neutrons. Also, quantitative analysis indicates that while the cold neutron temperature depends only slightly on the neutron absorption, the gain in cold neutron flux is strongly affected by the neutron absorption. 相似文献
18.
中子测井与天然气探测技术 总被引:3,自引:0,他引:3
简单介绍了中子测量与地层含氢指数及地层孔隙度的关系,介绍了地层含气对中子测量的影响以及泥浆侵入对中子在含气地层响应特征的影响.分析了中子测井仪器长短源距探测器受泥浆侵入影响的差异,给出了通过对中子仪器长短源距计数率校正消除泥浆侵入影响的方法.通过实际资料验证,取得了比较好的结果. 相似文献
19.
Cheikh M’Backé Diop Odile PetitCédric Jouanne Mireille Coste-Delclaux 《Annals of Nuclear Energy》2010
The probability table representation of cross-sections is generally used to deal with neutron interactions in the unresolved energy range. In the frame of neutron transport methods, the capability of the probability table representation of cross-sections on the whole neutron energy range has been mentioned by Cullen (1974) and it has been already demonstrated for the Monte Carlo transport calculations by Zheng et al. (1998). Such an advantage is also illustrated here with a simple neutron propagation configuration dealt with the TRIPOLI-4 Monte Carlo transport code. 相似文献