首页> 外文会议>ASME(American Society of Mechanical Engineers) Pressure Vessels and Piping Conference 2006 vol.7: Operations, Applications, and Components >FITNESS FOR SERVICE AND REMAINING LIFE ASSESSMENT FOR 1-1/4CR-1/2MO REACTOR SYSTEM PIPING ON A CATALYTIC REFORMER UNIT
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FITNESS FOR SERVICE AND REMAINING LIFE ASSESSMENT FOR 1-1/4CR-1/2MO REACTOR SYSTEM PIPING ON A CATALYTIC REFORMER UNIT

机译:催化重整装置上的1-1 / 4CR-1 / 2MO反应器系统的使用寿命和剩余寿命评估的适用性

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Fitness for service and remaining life assessment were performed on high temperature reactor piping to verify mechanical integrity for a desired remaining life.The NPS 20 1-1/4Cr-1/2Mo piping, which is the subject of this paper, was built in 1968 to the 1966 edition of ASA B31.3 for design conditions 465 psi at 950 °F / 365 psi at 1000 °F (3.16 Mpa at 510℃ / 2.48 Mpa at 538 ℃) for hydrogen and naphtha service. The actual operating conditions are 400 psi at 900 °F / 330 psi at 950 °F (2.72 Mpa at 482 ℃ / 2.24 Mpa at 510 ℃).Due to numerous reported failures in the industry in the 1980's, the ASME codes for piping and pressure vessels lowered the allowable stresses for low alloy steels operating in the creep range, mainly above 900 °F (482 ℃). Piping systems designed prior to changing the allowable stress do not satisfy today's codes.The operating stresses which can lead to failure from potential damage mechanisms, e.g. creep, reheat cracking and general corrosion, are defined and their impact on fitness-for-service and remaining life evaluated.Acceptance criteria for different types of defects were established prior to the unit maintenance turnaround by:1. Finite element modeling of assumed different degrees of weld peaking and pipe out-of-roundness for longitudinally welded pipe.2. Piping flexibility / stress analysis to identify areas with the highest operating stresses.3. Stresses from 1 and 2 above were used to calculate the creep life based on Larson-Miller parameter (API 530). Acceptable flaw sizes were limited by the desired remaining life.Inspection plans were developed to inspect for reheat cracking, creep damage, peaking, out of roundness, as well as general corrosion.
机译:NPS 20 1-1 / 4Cr-1 / 2Mo管道(建于1968年)是在高温反应堆管道上进行的适用性评估和对剩余反应堆寿命的评估,以验证机械完整性是否达到期望的剩余寿命。符合1966年版ASA B31.3的要求,设计条件是在950°F时为465 psi /在1000°F时为365 psi(510℃时为3.16 Mpa / 538℃为2.48 Mpa)。实际操作条件是900°F时为400 psi / 950°F时为330 psi(482℃时为2.72 Mpa / 510℃时为2.24 Mpa)。由于1980年代业界多次报道故障,ASME规范要求管道和压力容器降低了主要在900°F(482℃)以上运行的蠕变范围内的低合金钢的许用应力。在更改许用应力之前设计的管道系统不符合当今的规范。工作应力可能会导致潜在的损坏机制(例如定义了蠕变,再热裂纹和一般腐蚀,并评估了它们对使用寿命和剩余寿命的影响。在维修之前,通过以下方法建立了各种类型缺陷的验收标准:1。假定纵向焊接管具有不同程度的焊接峰化和管圆度的有限元建模2。配管灵活性/应力分析,以识别工作应力最大的区域3。来自上面1和2的应力用于基于Larson-Miller参数(API 530)计算蠕变寿命。可接受的缺陷尺寸受到所需的剩余寿命的限制。制定了检查计划以检查是否有再热裂纹,蠕变损伤,峰化,不圆度以及普遍腐蚀。

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