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Structural behavior during a PTS transient taking into account the WPS effect

机译:考虑WPS效应的PTS瞬态过程中的结构行为

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The Reactor Pressure Vessel (RPV) is an essential component limit the life duration of PWR's. Its behavior in service is limited in time due to the embrittling effects of irradiation. The structural integrity of the RPV is assessed by conventional fracture mechanical studies, where is assumed that the failure of a flawed structure occurs when the stress intensity factor at the crack tip reaches the toughness value of the structure material. Toughness curves of materials are obtained from monotonously increasing and isothermal loading. On the other hand, RPV integrity assessment involves loading conditions with coupled cooling, hearing, increasing and decreasing load.The safety analyses made at the European level study, the behavior of defects in the vessel subjected to loading resulting from thermal transients. These analyses usually do not take into account the effect of load history/warm pre-stressing (WPS) of the defects, which is observed in a wide range of experimental studies. The non-consideration of the beneficial effect of this physical phenomenon has two major consequences:· a poor knowledge of the real margins associated with the transients to which the vessel is subjected,· an economical penalty due to large under-estimation of the life duration of the vessel.This paper presents the results of two independent programs.The first dealing with four WPS tests performed at CEA in France on CT specimens manufactured of ferritic 18MND5 steel undergoing different types of loading during the cooling phase as follow:· Load Cool Fracture (LCF)·Loading Maintained CMOD Cooling Fracture (LM2CF)WPS effect observed in the first case, while curve in the second case the failure occurs during the crossing of the transition because of the monotonous increase of the force due to constant CMOD (Crack Mouth Opening Displacement).The second program deals with tests performed at MPA in Germany in collaboration with EDF on CT25 and CT50 specimens using the same material with five types of WPS cycles:· LCF· Load Unload Cool Fracture (LUCF)· Load Transient Fracture (LTF)· Load Oscillation Cool Fracture (LOCF)· Load Oscillation Transient Fracture (LOTF)In all these cases, WPS effect is demonstrated.For both the programs, numerical analyses were performed at MPA using Weibull (Metall Trans A, 14A (1987) 2277) and Chell (Fourth Int Conf Pressure Vessel Technol, Inst Mech Engng, 1980, Paper C22/80, London, U.K. 117) models to predict the WPS effect, details of which are presented here.
机译:反应堆压力容器(RPV)是限制PWR使用寿命的重要组成部分。由于辐射的脆化作用,其使用中的行为在时间上受到限制。 RPV的结构完整性通过常规断裂力学研究进行评估,其中假定当裂纹尖端处的应力强度因子达到结构材料的韧性值时,就会出现缺陷结构的失效。材料的韧性曲线是从单调增加的载荷和等温载荷获得的。另一方面,RPV完整性评估涉及负载条件以及冷却,听觉,负载增加和减小的耦合。在欧洲一级进行的安全性分析研究中,热瞬变导致负载下容器缺陷的行为。这些分析通常不考虑缺陷的载荷历史/热预应力(WPS)的影响,这在广泛的实验研究中都可以观察到。不考虑这种物理现象的有益效果有两个主要后果:·对与船舶所遭受的瞬变有关的实际余量的了解不足,·由于对寿命的低估而造成的经济损失本文介绍了两个独立程序的结果。第一个程序处理在法国CEA对由18MND5铁素体铁素体制成的CT试样在冷却阶段进行不同载荷的四个WPS测试,如下所示:·载荷冷断裂(LCF)·在第一种情况下观察到的载荷保持CMOD冷却断裂(LM2CF)WPS效果,而在第二种情况下,由于在恒定的CMOD力的作用下单调增加,因此在过渡相交时发生弯曲失败开口位移)。第二个程序处理在德国MPA上与EDF合作进行的测试,该测试使用的是相同材质的FI25在CT25和CT50上WPS循环的以下几种类型:·LCF·负荷卸载冷断裂(LUCF)·负荷瞬态断裂(LTF)·负荷振荡冷断裂(LOCF)·负荷振荡瞬态断裂(LOTF)在所有这些情况下,都证明了WPS效果。在这两个程序中,均使用Weibull(Metall Trans A,14A(1987)2277)和Chell(Fourth Int Conf压力容器技术,Inst Mech Engng,1980,Paper C22 / 80,伦敦,英国117)模型在MPA上进行了数值分析。预测WPS效果,有关详细信息,请参见此处。

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