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现行 API TR 934-H
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Inspection, Assessment, and Repair of Heavy Wall Reactor Vessels in High-temperature High-pressure Hydrogen Service, First Edition 高温高压氢气设施中厚壁反应堆容器的检查、评估和维修 第一版
发布日期: 2022-05-01
本TR记录了厚壁反应堆容器(标称壁厚为50 mm(2 in.)的)的检查、评估和维修指南和更高)在455°C(850°F)以下的温度下运行的高压氢气服务中。它提供了在建造和暴露于操作条件后处理反应堆容器的行业实践。重点介绍了由2?Cr-1Mo、3Cr-1Mo、2?Cr-1Mo-V和3Cr-1Mo-V钢制成的反应堆容器。它还为1Cr制造的厚壁反应堆容器提供了一些指导- Mo和1 Cr-Mo钢,但具体不适用于C-Mo钢容器。然而,本文件中包含的指南可用于碳钼钢反应堆容器,由业主自行决定,并根据需要进行修改。本文件不涉及热壁催化重整反应器、流化催化裂化装置(FCCU)反应器和延迟焦化罐中发现的损坏,因为它们通常在较高温度下运行,且壁较薄。由于这是一份技术报告,因此它不提供建议,而是介绍了维修案例和公认实践的行业经验,其中大部分记录为1995年至2004年间分两个阶段进行的老化反应堆容器联合行业计划(JIP)的一部分。
This TR documents guidance for the inspection, assessment, and repair of heavy wall reactor vessels (nominally considered a wall thickness of 50 mm (2 in.) and greater) in high-pressure hydrogen service operating at temperatures below 455 °C (850 °F). It provides industry practices dealing with reactor vessels after construction and exposure to operating conditions. It focuses on reactor vessels fabricated from 2¿Cr-1Mo, 3Cr-1Mo, 2¿Cr-1Mo-¿V, and 3Cr-1Mo-¿V steels. It also offers some guidance for heavy wall reactor vessels fabricated from 1Cr-¿Mo and 1¿Cr-¿Mo steels, but specifically does not pertain to C-¿Mo steel vessels. However, guidance included in this document can be used for C-¿Mo steel reactor vessels at the owner's discretion and with modifications as appropriate.This document does not address damage found in hot wall catalytic reforming reactors, fluid catalytic cracking unit (FCCU) reactors, and delayed coking drums as they generally operate at higher temperatures and have thinner walls.Since this is a technical report, it does not provide recommendations, but instead presents industry experience with case histories of repairs and recognized practices, much of which was documented as part of a Joint Industry Program (JIP) on Aging Reactor Vessels, conducted in two phases between 1995 and 2004.
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发布单位或类别: 美国-美国石油学会
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