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Replacement of VVER-440 Reactor-coolant-pump Main-flange Packing

机译:更换VVER-440反应堆冷却剂泵主法兰盘根

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Reactor Coolant Pump (RCP) of the VVER-440 nuclear power plant is a vertical centrifugal pump equippedrnwith a mechanical gland, electric drive and auxiliary systems. Up to now, its thrust flange is sealed by a flatrnmetal (austenitic) packing which is situated in the main force flow and forms a cover of the pump.rnIn the working condition, the RCP flange joint is exposed to a force and thermal load action. The force loadrncovers the media internal overpressure effect and forces in stud-bolts. The thermal load results from arntemperature distribution in the pump wall (stationary and non-stationary thermal field), eventually it may berncaused by parts which have dissimilar thermal expansivity and which can’t dilate freely.rnComputing fatigue damage cumulations performed after 10 years of operation at Unit 1 of NPP Dukovany inrnthe mostly stressed parts of the thrust cover and the RCP-casing flange showed out values ranging from 0.908 torn3.49. The results evidenced definitely that it was necessary to take actions which would reduce the tenseness inrncritical parts of the RCP flange and cover. We’ve chosen an option to modify the seating face so that we couldrnseparate the shape stress concentration from the edge stress concentration through a recess machined in the face,rnwhich would enable to remove the stress raiser. It was necessary to design its shape so that it would resolve thernproblem of the reduced life-time and, at the same time, it would be possible to realize the modification right inrnthe power plant.rnFurthermore, we’ve looked for a method of reduction of the tightening forces in the stud-bolts which cause arnplastic deformation of the sealing-surface material (for the austenitic packing it is 1180 kN per 1 stud-bolt).rnA new flange-joint packing (located in the main force flow) has been designed - a graphite ridge-shapedrnpacking consisting of a steel core with grooves machined in its both surfaces (so called ridges), and foils (with arnthickness of 0.75 mm) made of expanded graphite which are pressed into the ridges. This packing is seated at arnwider surface of the pump casing than it was in case of the original austenitic packing. Calculations have beenrnmade according DIN 2505 and EN 1591 standards in order to check a pressure in the packing at all possible loadrncases. In sum, 31 stress fields for 31 stress conditions have been calculated.rnThe calculations have demonstrated that the newly designed ridge-shaped packing together with the graphiternfoils is capable to assure the tightness of the RCP flange joint while at the same time using significantly reducedrntightening forces in the stud-bolts. The newly recommended tightening force is 588 kN compared to the one ofrn1180 kN used in case of the austenitic packing. This way we happen to reduce significantly the tenseness in thernstud-bolts. The reduced tenseness is present also in the pump casing in points where the new packing is installed,rnthus we achieve an extended RCP service life.rnThe packing was tested, according to DIN 28090-1 and prEN 13555 standards, at a testing bench at anrnaccredited laboratory in NRI Rez (Nuclear Research Institute). The tests have demonstrated definitely therntightness of the joint with the use of the ridge-shaped packing. It will enable, together with NDT tests performedrnat the RCP casing (note : no indications found so far), to extend the RCP inspection interval, thus to save thernmaintenance cost and to reduce radiation doses of the personnel.rnThrough resolving the RCP main-flange lifetime, NPP Dukovany has become the first and so far the lastrnVVER-type nuclear power plant that has happened to successfully cope with the problem.
机译:VVER-440核电站的反应堆冷却剂泵(RCP)是一种立式离心泵,配有机械密封管,电驱动和辅助系统。到目前为止,其推力法兰已通过扁平金属(奥氏体)填料密封,该填料位于主力流中并形成泵的外盖。在工作状态下,RCP法兰接头承受力和热负荷作用。力负载覆盖了介质内部的超压效应和双头螺栓中的力。热负荷是由泵壁上的温度分布(静态和非静态热场)产生的,最终可能是由热膨胀率不同且不能自由膨胀的零件造成的。计算运行10年后的疲劳损伤累积量在NPP Dukovany的1号机组,推力盖和RCP机壳法兰中受压最严重的部分的值在0.908至3.49之间。结果明确表明,有必要采取措施减少RCP法兰和盖板的紧张非关键部分。我们选择了一种修改阀座面的选项,以便我们可以通过在面上加工出的凹口将形状应力集中与边缘应力集中分离开来,从而可以消除应力提升器。有必要对其形状进行设计,以解决其使用寿命减少的问题,同时,有可能在电厂中实现修改。rn此外,我们正在寻找一种简化方法。导致密封表面材料发生塑性变形的双头螺栓紧固力(对于奥氏体填料,每1个双头螺栓为1180 kN)。rn新的法兰接头填料(位于主力流中)具有设计了一种石墨山脊形填料,包括一个在其两个表面上都加工有凹槽的钢芯(所谓的山脊),以及由膨胀石墨制成的箔(厚度为0.75毫米),被压入山脊中。与原始奥氏体填料相比,该填料位于泵壳体的更宽的表面上。根据DIN 2505和EN 1591标准进行了计算,以便在所有可能的载荷情况下检查填料中的压力。总的来说,计算了31种应力条件下的31个应力场。计算表明,新设计的脊形填料与石墨箔一起能够确保RCP法兰接头的密封性,同时显着降低了紧固力在双头螺栓中。新推荐的紧固力为588 kN,而奥氏体填料的紧固力为1180 kN。这样,我们碰巧大大降低了螺栓的张力。在安装新填料的位置,泵壳中也出现了降低的张力,从而延长了RCP的使用寿命。rn根据DIN 28090-1和prEN 13555标准对填料进行了测试,并在经过认可的测试台上进行了测试。 NRI Rez(核研究所)的实验室。这些测试已明确证明了使用脊形填料可以保证接头的密封性。它将与在RCP外壳上进行的NDT测试(注意:到目前为止没有发现)一起,能够延长RCP检查间隔,从而节省维护成本并减少人员的辐射剂量。 NPP杜科瓦尼(NPP Dukovany)一生中已经成为成功解决该问题的第一个也是迄今为止最后一个VVER型核电厂。

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