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Information about the sorption of radionuclides on natural materials used for cementation of liquid radioactive wastes (RAW) is important for predictions of migration rates of radionuclides in the products of fixation. Cementation process for conditioning liquid RAW uses, besides cement, materials which improve quality of products. In Czechoslovakia technology among these materials are clinoptilolite tuffit, mordenite tuff, tobermorite and fly ash. Liquid RAW issued from nuclear power plants contains the principal radionuclides60Co,134Cs and137Cs, therefore, a sorption study of these radionuclides was carried out. pH of liquid RAW was 12.5–13.7 and salt content ca. 200 g·dm–3. Results of sorption are given by distribution coefficients. The best results for cesium in those pH region and salt content had mordenite tuff DCs=100 dm3·kg–1 and the worst results had fly ash DCs=4.1 dm3·kg–1. The best results for cobalt in those solutions had tobermorite DCo=38 dm3·kg–1 and the worst results had fly ash DCo=6.9 dm3·kg–1. 相似文献
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应用锥压缩锥拉伸不动点定理和Leray-Schauder 抉择定理研究了一类具有P-Laplace算子的奇异离散边值问题$$\left\{\begin{array}{l}\Delta[\phi (\Delta x(i-1))]+ q_{1}(i)f_{1}(i,x(i),y(i))=0, ~~~i\in \{1,2,...,T\}\\\Delta[\phi (\Delta y(i-1))]+ q_{2}(i)f_{2}(i,x(i),y(i))=0,\\x(0)=x(T+1)=y(0)=y(T+1)=0,\end{array}\right.$$的单一和多重正解的存在性,其中$\phi(s) = |s|^{p-2}s, ~p>1$,非线性项$f_{k}(i,x,y)(k=1,2)$在$(x,y)=(0,0)$具有奇性. 相似文献
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Mina Guli Xiaotian Li Kan Zhang Yue Chi 《Journal of Sol-Gel Science and Technology》2010,54(3):329-334
Large, flawless and transparent silica monoliths were prepared at room temperature by solvent evaporation method and loaded
with dye. The composites containing dye molecules were characterized by X-ray diffraction, transmission electron microscopy,
Uv–vis and photoluminescence spectra. A red-shift in photoluminescence spectrum was observed from the composite monolith compared
with that of laser dye in C2H5OH solution. The property of laser narrowing has been shown when the composites are pumped at p = 355 nm by nitrogen laser. 相似文献
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N. V. Guličev 《Analysis Mathematica》1980,6(4):269-280
Пусть ω(δ) - модуль непре рывности,H ω — класс 1-периодических непре рывных функцийf (t), модуль непрерывнос ти которыхω(f, δ)≦ω(δ), и п устьS n (f,x)=S n (f),D n (t), Ln – соответственно ча стичные суммы ряда Фу рье-Уолшаf(t), ядра Дирихле и конст анты Лебега порядкап (п- 1, 2, ...). Доказаны Теорема 1.Для любой не прерывной функции f $$\mathop {\lim \inf }\limits_{k \to \infty } \frac{{\parallel f - S_k (f)\parallel }}{{\omega (f,1/k)L_k }} = 0$$ Теорема 2.Пусть 0n=[nβ]+1 (n=1,2, ...). Пусть, далее, Мn — множество тех k (2nk<2n+1), для которых Тогда в каждом классе $$\int\limits_0^{2^{ - m_n } } {\left| {D_k (t)} \right|dt \geqq AL_k } $$ найдется функция f, т акая, что $$\mathop {\lim \inf }\limits_{k \in \mathop \cup \limits_n M_n } \frac{{\left\| {f - S_k (f)} \right\|}}{{\omega (1/k)L_k }} \geqq B(A) > 0$$ 相似文献
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G. Guliš 《Journal of Radioanalytical and Nuclear Chemistry》1991,150(2):261-267
The incineration is one of the widely used method for treatment of solid radioactive wastes. The high volume and weight reduction coefficient (100–150 respectively 10–15) are advantages of this method. The greater part of radionuclides from solid radioactive wastes is retained in ash. From point of view of workers external irradiation, the radionuclides accumulation in furnace lining is one of risk factors. The Kalinit O 1200 is furnace lining material on NPPRIs Experimental Incineration facility. In the first step the sorption properties of this material from137Cs,60Co,54Mn,65Zn solutions were studied. The best results had60Co, its distribution coefficient was 7036 kg · dm–3. Cesium-137 was not absorbed on this material. The cylinders (height 5 cm, diameter 2 cm) from lining materials were made latest and were applicated inside the furnace and technological tract to study sorption properties from combustion gases. The penetration of radionuclide into lining material was studied too. The results obtained with this experiments are described in this paper. 相似文献
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The antioxidant Lowinox 22M46 (Naftonox 22M46) were used for the extraction of cesium from intermediate level liquid radioactive wastes. 相似文献