Test data for uniaxial tensile on material INCONEL 617 irr at 20 Celsius

The Alloy 617 creep rupture data were determined for the high temperature reactor projects (the direct cycle helium turbine project, the nuclear process heat project and the district heating project) of the Federal Republic of Germany and the State of North Rhine Westphalia, the aim being to qualify the alloy for service at temperatures up to 950°C. Alloy 617 was the prime candidate alloy for construction of the He-He intermediate heat exchanger and hot gas ducting. Several batches and product forms (forged bar, rolled plate, pipes and tubes) of the alloy were investigated and special attention was given to the effects of the service environments (helium containing different impurity gases, such as hydrogen, water vapour, carbon monoxide and methane, all at microbar levels, and methane reforming gas mixture) on the properties. In the test machines, these test environments led to carburisation of test pieces. However, analysis of the data showed that the stress rupture data for tests in air, in impure helium and in methane reforming gas lay in the same scatter band at each temperature tested.

The creep rupture tests were carried out in single-specimen and multi-specimen test machines. In the single specimen machines the strain was continuously monitored and strain readings were taken once a day. In the multi-specimen test rigs, there were six strings, each with a different load. There were up to eight test pieces per string and strain measurements were made by interrupting the tests, cooling to room temperature, then measuring the length of each test piece using a travelling microscope. Test interruptions for strain measurements were generally every 1000 h. The tests were carried out according to the German Standard DIN 50118 (1982).

The data (secondary creep rate, time to 1% strain, time to rupture) were used for the formulation of draft nuclear design rules for the high temperature reactor systems, which are summarised in 'Proceedings of the Workshop on Structural Design Criteria for HTR', G Breitbach, F Schubert, H Nickel, Jül-Conf-71, April 1989, Berichte der Kernforschungsanlage Jülich GmbH, ISSN 0344-5798.

In addition to the creep rupture data, Alloy 617 tensile properties, low cycle fatigue and creep crack growth data are stored in MatDB.

本数据集包含合金617（Alloy 617）的蠕变断裂数据，相关测试依托德意志联邦共和国与北莱茵-威斯特伐利亚州的高温反应堆项目展开，涵盖直接循环氦气轮机项目、核工艺热项目及区域供热项目，旨在使该合金获得最高950℃服役工况下的使用资质。合金617是氦-氦中间热交换器（He-He intermediate heat exchanger）与热气体导管建造的首选候选合金。
研究团队对该合金的多批次样品与多种产品形态（锻造棒材、轧制板材、管材）开展了测试，并重点关注服役环境对合金性能的影响：试验环境包括含微量杂质气体（氢气、水蒸气、一氧化碳、甲烷，均处于微巴级别）的氦气，以及甲烷重整混合气体。在试验机中，上述试验环境会导致试样发生渗碳现象。但数据分析显示，在空气、不纯氦气与甲烷重整气体中开展试验得到的应力断裂数据，在各测试温度下均处于同一散射区间内。
蠕变断裂试验分别通过单试样试验机与多试样试验机完成。单试样试验机中，应变被连续监测，且每日记录一次应变数据。多试样试验台分为6组，每组施加不同载荷；每组最多搭载8个试样，应变测量需通过中断试验、冷却至室温后，使用读数显微镜（travelling microscope）测量每个试样的长度完成。应变测量的试验中断周期通常为每1000小时一次。所有试验均依据德国标准DIN 50118（1982版）执行。
本数据集包含的二次蠕变速率、1%应变对应的时间、断裂时间等数据，被用于制定高温反应堆系统的核设计规范草案，相关内容总结于《高温气冷堆（High Temperature Reactor, HTR）结构设计准则研讨会论文集》，原标题为'Proceedings of the Workshop on Structural Design Criteria for HTR'，作者为G Breitbach、F Schubert、H Nickel，会议编号Jül-Conf-71，1989年4月，收录于于利希核研究中心有限公司报告（Berichte der Kernforschungsanlage Jülich GmbH），国际标准刊号ISSN 0344-5798。
除蠕变断裂数据外，合金617的拉伸性能、低周疲劳及蠕变裂纹扩展数据均存储于MatDB数据库中。