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首页> 外文期刊>The Paton Welding Journal >INVESTIGATION OF STRESS-STRAIN STATE OF WELDED STRUCTURES FROM AUSTENITIC STEEL AT RADIOACTIVE IRRADIATION
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INVESTIGATION OF STRESS-STRAIN STATE OF WELDED STRUCTURES FROM AUSTENITIC STEEL AT RADIOACTIVE IRRADIATION

机译:奥氏体钢在辐射辐照下的焊接组织的应力-应变状态研究

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Nuclear reactor reflection shield is exposed to high doses of radiation, leading to its noticeable deformation and closing of the clearance between the reflection shield and cavity wall. This leads to a change of heat exchange in the reactor core that may have hazardous consequences in terms of violation of temperature mode of reactor operation. To evaluate the radiative swelling of the reflection shield, a 2D finite element model was constructed, using calculation algorithms well-tested at the E.O. Paton Electric Welding Institute, in which isotropic volumetric deformations were assigned as radiative swelling. The model nonlinearly takes into account the dependence of radiative swelling of the reflection shield material on irradiation temperature, stressed state and plastic deformations. The model also describes the change of yield limit of welded cavity wall, as a function of irradiation temperature and accumulated radiation dose. After 25 years of reactor operation the maximum value of swelling deformations in reflection shield material is equal to 1,3%, reaching 1.8 after 40 years, and 3.7 after 60 years. Maximum radial displacements of the reflection shield outer surface during reactor operation are equal to 11.2 mm after 25 years, 12.9 mm after 40 years, and 16.1 mm after 60 years. In a more conservative model, not allowing for the history of volumetric deformation accumulation, reflection shield swells by 26% over 60 years of operation that corresponds to even greater radial displacements of reflection shield outer surface in the outward direction. Results on swelling and radial deformations of the reflection shield derived allowing for the stressed state are indicative of a possible contact of reflection shield with the cavity welded wall during reactor operation. Such a contact can greatly affect the stress-strain state of the cavity welded structure, therefore, it requires a more detailed study.
机译:核反应堆反射罩暴露于高剂量的辐射下,导致其明显变形,并关闭了反射罩与腔壁之间的间隙。这导致反应堆堆芯中热交换的变化,这可能会违反反应堆运行的温度模式而产生危险后果。为了评估反射罩的辐射膨胀,使用在E.O上经过良好测试的计算算法,构建了2D有限元模型。帕顿电焊研究所(Paton Electric Welding Institute),其中各向同性的体积变形被指定为辐射膨胀。该模型非线性地考虑了反射屏蔽材料的辐射膨胀对辐射温度,应力状态和塑性变形的依赖性。该模型还描述了焊接腔壁屈服极限随辐照温度和累积辐照剂量的变化。在反应堆运行25年后,反射屏蔽材料的溶胀变形最大值等于1,3%,在40年后达到1.8,在60年之后达到3.7。反应堆运行期间,反射罩外表面的最大径向位移等于25年后为11.2毫米,40年后为12.9毫米,60年后为16.1毫米。在一个更为保守的模型中,考虑到体积变形累积的历史,反射屏蔽在使用60年后膨胀了26%,这对应于反射屏蔽外表面在向外方向上的更大径向位移。所得出的允许应力状态的反射罩的膨胀和径向变形的结果表明在反应堆运行期间反射罩可能与空腔焊接壁接触。这种接触会极大地影响型腔焊接结构的应力-应变状态,因此,需要进行更详细的研究。

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