摘要:
The present invention relates to a compound having the following general formula (I): ##STR1## wherein X stands for a halogen atom or a methyl radical; and R stands for an alkyl or alkoxy radical containing 3 to 6 carbon atoms provided that R represents an alkyl radical containing 3 to 6 carbon atoms when X is a methyl radical, a process for the production thereof, an agricultural composition containing the said compound as an effective component, and a method for preventing and healing the diseases of the plant and in soil using the said compound.
摘要:
2,4-Dimethyl-3-carboxanilido- or naphthyl amido-furan of the formula ##SPC1##Involving the reaction of ##SPC2##Or ##SPC3##Wherein X represents a halogen atom, an alkyl group, hydroxyl group, an alkoxyl group, an alkenyloxy group, trifluoromethyl group, phenyl group, cyano group, acetyl group, a metal substituted hydroxy group or a combination thereof are useful as agricultural germicides, fungicides, insecticides and nematodicides.
摘要:
A corrosion resistant zirconium alloy for use as a nuclear reactor cladding material. This alloy consists essentially of, on a weight % basis 0.02-1.7 % Sn, 0.19-0.6% Fe, 0.07-0.4% Cr, 0.01-0.2% Ta, and optionally 0.05 up to less than 0.5% Nb, the balance being Zr and incidental impurities, provided that the content of the nitrogen in the form of incidental impurities is no more than 60 ppm.
摘要:
A fuel rod for a light water reactor comprises a cladding tube which comprises a zirconium alloy having a composition including 0.6 to 2.0% by weight of Nb, 0.5 to 1.5% by weight of Sn, 0.05 to 0.3% by weight of Fe, and the balance being Zr and incidental impurities; uranium oxide fuel pellets packed in the cladding tube; and end plugs closing both ends of the cladding tube. The cladding tube is sealed by TIG welding with the end plugs. Precipitates having grain diameters of 0.01 to 0.5 .mu.m and comprise intermetallic compounds containing Zr, Nb and Fe are present at grain boundaries in the structure of heat affected zones of the cladding tube, the heat affected zone being adjacent to a bead formed by TIG welding.
摘要:
A fuel rod for a light water reactor comprises a cladding tube which comprises a zirconium alloy having a composition including 0.6 to 2.0% by weight of Nb, 0.5 to 1.5% by weight of Sn, 0.05 to 0.3% by weight of Fe, and the balance being Zr and incidental impurities; uranium oxide fuel pellets packed in the cladding tube; and end plugs comprising a zirconium alloy and closing both ends of the cladding tube. The cladding tube is sealed by TIG welding with the end plugs. Grain boundaries in each heat affected zone of the cladding tube, which are adjacent to a bead formed by TIG welding, have structural compositions including 4 to 30% by weight of Nb, and 0.9 to 20% by weight of Fe.
摘要:
A corrosion resistant zirconium alloy for use as a nuclear reactor cladding material. This alloy consists essentially of, on a weight % basis 0.02-1.15% Sn, 0.19-0.6% Fe, 0.07-0.4% Cr, and optionally 0.05 to not more than 0.5% Nb, the balance being Zr and incidental impurities, provided that the content of the nitrogen in the form of incidental impurities is no more than 60 ppm.
摘要:
The invention provides a method for making Zr alloy nuclear reactor fuel cladding having excellent corrosion resistance and creep properties. The method includes performing hot forging, solution heat treatment, hot extruding, and repeated cycles of annealing and cold rolling of a Zr alloy including, by weight, 0.2 to 1.7% Sn, 0.18 to 0.6% Fe, 0.07 to 0.4% Cr and 0.05 to 1.0% Nb, with the remainder being Zr and incidental impurities, and the incidental nitrogen impurity content being 60 ppm or less, and then performing final stress relief annealing thereon. The annealing is performed at a temperature of 550.degree. C. to 850.degree. C. for 1 to 4 hours such that the accumulated annealing parameter .SIGMA.Ai=.SIGMA.ti.multidot.exp(-40,000/Ti) satisfies relationships -20.ltoreq.log.SIGMA.Ai.ltoreq.-15, and -18-10.multidot.X.sub.Nb .ltoreq.log.SIGMA.Ai.ltoreq.-15-3.75.multidot.(X.sub.Nb -0.2), wherein Ai represents the annealing parameter for the i-th annealing, ti represents the annealing time (hours) for the i-th annealing, Ti represents the annealing temperature (K) for the i-th annealing, and X.sub.Nb represents the Nb concentration (wt %).
摘要翻译:本发明提供了一种制造具有优异的耐腐蚀性和蠕变性的Zr合金核反应堆燃料包覆的方法。 该方法包括进行热锻,固溶热处理,热挤压以及Zr合金的退火和冷轧的重复循环,所述Zr合金的重量为0.2〜1.7%的Sn,0.18〜0.6%的Fe,0.07〜0.4%的Cr和0.05 至1.0%的Nb,其余为Zr和杂质,偶氮含量为60ppm以下,然后对其进行最终的应力消除退火。 退火在550℃至850℃的温度下进行1至4小时,使得累积退火参数SIGMA Ai = SIGMA tixexp(-40,000 / Ti)满足关系-20 log SIGMA Ai < / = -15,和-18-10xXNb = log SIGMA Ai - 〜35-34 .75x(XNb-0.2),其中Ai表示第i次退火的退火参数,ti表示退火时间 ),Ti表示第i次退火的退火温度(K),XNb表示Nb浓度(wt%)。