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71.
72.
《Journal of Nuclear Science and Technology》2013,50(8):1126-1130
Potential of DT fusion neutron source to enhance proliferation resistance properties of plutonium by means of its isotopic denaturing is addressed. The approach is exemplified by denaturing of pure 239Pu and plutonium of typical LWR spent fuel through transmutation of neptunium. The essential feature of a fusion driven system proposed in the study is a zero mass balance of plutonium: total plutonium inventory is constant during irradiation. The system is capable to convert pure 239Pu into plutonium composition with more than 20% fraction of key 238Pu isotope during 1,000 d of irradiation under initial neutron loading of 1 MW.m?2. Denaturing of LWR spent fuel plutonium under the same conditions would increase its 238Pu content up to 10-12%. 相似文献
73.
《Journal of Nuclear Science and Technology》2013,50(6):911-918
An autoradiographical method using an imaging plate (IP) was developed to analyze plutonium contamination in a plutonium handling facility. The IPs were exposed to ten specimens having a single plutonium particle. Photostimulated luminescence (PSL) images of the specimens were taken using a laser scanning machine. One relatively large spot induced by α-radioactivity from plutonium was observed in each PSL image. The plutonium-induced spots were discriminated by a threshold derived from background and the size of the spot. A good relationship between the PSL intensities of the spots and α- radioactivities measured using a radiation counter was obtained by least-square fitting, taking the fading effect into consideration. This method was applied to workplace monitoring in an actual uraniumplutonium mixed oxide (MOX) fuel fabrication facility. Plutonium contaminations were analyzed in ten other specimens having more than two plutonium spots. The α-radioactivities of plutonium contamination were derived from the PSL images and their relative errors were evaluated from exposure time. 相似文献
74.
75.
Kazumi Ikeda Richard A. Kochendarfer Shigeru Kunishima 《Nuclear Engineering and Design》2011,241(5):1438-1453
This paper presents about conceptual designs of Advanced Recycling Reactor (ARR) focusing on enhancement in transuranics (TRU) burning and americium (Am) transmutation. The design has been conducted in the context of the Global Nuclear Energy Partnership (GNEP) seeking to close nuclear fuel cycle in ways that reduce proliferation risks, reduce the nuclear waste in the US and further improve global energy security. This study strives to enhance the TRU burning and the Am transmutation, assuming the development of related technologies in this study, while the ARR based on mature technologies was designed in the previous study. It has followed that the provided TRU burning core is designed to burn TRU at 28 kg/TWthh, by adding moderator pins of B4C (Enriched B-11) and the Am transmutation core will be able to transmute Am at 34 kg/TWthh, by locating Am blanket of AmN around the TRU burning core. It indicates that these concepts improve TRU burning by 40-50% than the previous core and can transmute Am effectively, keeping the void reactivity acceptable. 相似文献
76.
77.
Abstract Diamylamyl phosphonate (DAAP) was synthesised by the Michealis Becker reaction, and was characterized by elemental analysis, IR, and 31P NMR. The extraction of U(VI), Th(IV), Pu(IV) and Am(III) by 1.1 M DAAP in n‐dodecane as a function of nitric acid concentration was studied and the results are compared with the extraction behavior of these ions by tributyl phosphate (TBP) and triamyl phosphate (TAP) in n‐dodecane. Some important physical properties of the extractant that have to be met for its use in industrial scale liquid‐liquid extraction such as density, surface tension, viscosity and phase disengagement time with 1.1 M DAAP/n‐dodecane have been measured and compared with those of 1.1 M TBP/n‐dodecane. Studies on the third phase formation behavior of DAAP/n‐dodecane with U(VI) and Th(IV) nitrates in nitric acid medium have been carried out and the results are reported. The breakthrough and elution behavior of U(VI) using a column packed with 50% (w/w) DAAP impregnated on Amberlite XAD‐7 was studied and reported. 相似文献
78.
研究了Pu存在条件下HNO2氧化U(Ⅳ)的反应,并考察了HNO2浓度、反应温度、HNO3浓度、Pu浓度对U(Ⅳ)氧化速率的影响。结果表明:Pu对HNO2氧化U(Ⅳ)的反应具有显著催化作用;获得了Pu催化条件下HNO2氧化U(Ⅳ)的动力学方程:-dc(U(Ⅳ))/dt=kc(U(Ⅳ))c1.3(HNO3)c1.3(NO-2),得到了29℃时的反应速率常数k=(0.69±0.04)L2.6/(mol 2.6·min)。并对反应历程进行了探讨。 相似文献
79.
为了了解溶剂在乏燃料后处理真实使用过程的辐解稳定性,对比研究了30%TBP-煤油-HNO3体系在γ和α的静态累积辐照和动态循环辐照情况下的辐解行为。研究结果表明:静态累积辐照所引起的溶剂辐解产物生成量、钚保留和钌保留等性能的变化比动态循环辐照明显;当辐照吸收剂量达到1.0×105 Gy(相当于动态循环辐照20次)时,静态累积辐照引起的溶剂钚保留值10倍于动态循环辐照,证实了在乏燃料后处理工艺过程中,通过溶剂的酸碱洗涤,去除HDBP、H2MBP等主要辐解产物,可提高溶剂的循环使用寿命。同时研究结果显示,溶剂的α辐照损伤大于γ辐照。 相似文献
80.
V.I. Terekhov M.A. Pakhomov 《International Journal of Heat and Mass Transfer》2009,52(21-22):4711-4721
Droplets-laden turbulent flow downstream of a sudden pipe expansion has been investigated by using Euler/Euler two-fluid model for the gaseous and dispersed phases. Significant increase of heat transfer in separated flow at the adding of evaporating droplets has been demonstrated (more than 2 times compare with one-phase flow at the value of mass concentration of droplets ML1 0.05). Addition of dispersed phase to the turbulent gas flow results in insignificant increase of the reattachment length. Low-inertia droplets (d1 50 μm) are well entrained into the circulation flow and present over the whole pipe section. Large particles (d1 ≈ 100 μm) go through the shear layer not getting into the detached area. Comparison with experimental data on separated gas–droplets flows behind the plane backward-facing step has been carried out. 相似文献