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首页> 外文会议>International Conference on Structural Mechanics in Reactor Technology >ON THE DEVELOPMENT OF CT-TYPE SPECIMEN FROM WER-1000 SURVEILLANCE SPECIMEN MATERIALS RECONSTRUCTION PROCEDURE
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ON THE DEVELOPMENT OF CT-TYPE SPECIMEN FROM WER-1000 SURVEILLANCE SPECIMEN MATERIALS RECONSTRUCTION PROCEDURE

机译：从WER-1000监视标本材料重建程序开发CT型标本

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A reliable evaluation of current status of reactor pressure vessel (RPV) and determination of its lifetime necessitate receiving direct data of material fracture toughness which are used in RPV resistance to brittle fracture calculations. The fracture toughness data for reactors placed in commission before 2002 can be obtained only with small-size specimens (of 10×10-mm cross-section) of SE(B)-type that are included in WER-1000surveillance specimens programs. The reactors placed in commission after 2002 and all new projects of reactor plants have surveillance specimens located on internal surface of pressure vessel in flat containers that provide for accommodation of full-scale specimens of CT-type; the testing data for these specimens give more accurate information on fracture toughness. This paper suggests to use test results of reconstructed specimens of CT-type made of halve-pieces of Charpy or SE(B)-type tested specimens using electron-beam welding to enhance of the forecast dependence of fracture toughness as compared to that obtained with SE(B)-type specimens. We have prepared reconstructed specimens of CT-type with insertions sized 10×10 mm and 20×10 mm. While making welded seams, the insertion temperature was measured in the place of anticipated fracture location. Tests and fractographic examinations were carried out to study reconstructed and non-reconstructed specimens. The analysis have confirmed fine precision of test results for non-reconstructed specimens of CT-type. The fracture toughness test results for non-reconstructed and reconstructed specimens and structural peculiarities of fractures testified that employed reconstruction procedures produce no significant influence on the mechanisms of brittle fracture origination and characteristics of fracture toughness specimens.
机译：要对反应堆压力容器（RPV）的当前状态进行可靠的评估并确定其使用寿命，必须接收直接用于RPV抵抗脆性断裂计算的材料断裂韧性数据。只有使用WER-1000监测标本计划中包含的SE（B）型小型标本（横截面为10×10 mm）才能获得2002年之前投入运行的反应堆的断裂韧性数据。 2002年以后投入运行的反应堆以及所有新的反应堆项目，在压力容器内表面的扁平容器中装有监测标本，可容纳CT型全尺寸标本。这些样品的测试数据可提供有关断裂韧性的更准确信息。本文建议使用电子束焊接对半夏比或SE（B）型试样两半制成的CT型重建试样的测试结果，以增强对断裂韧性的预测依赖性。 SE（B）型标本。我们准备了插入尺寸为10×10 mm和20×10 mm的CT型重建标本。在制作焊缝时，在预期断裂位置的位置测量插入温度。进行了测试和分形检查，以研究重建和未重建的标本。分析证实了未经重建的CT型标本的测试结果具有较高的精确度。非重建和重建标本的断裂韧性测试结果以及断裂的结构特性证明，采用重建程序对脆性断裂的产生机理和断裂韧性标本的特性没有显着影响。

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