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In the oil and gas industry, solid metal equipment such as pipelines, pressure vessels, heat exchangers and valves are susceptible to surface cracks and discontinuities attributed to cyclic loading, process environment and severe operating conditions. These anomalies affect the safety, structural functionality, reliability, integrity and life cycle of the equipment. They could lead to catastrophic incidents if not detected timely, evaluated, monitored and properly repaired.
Stress Corrosion Cracking (SCC) models are important for engineering and regulatory assessments. The SCC time to the growth of a crack of engineering scale is the main fraction of component life prior to failure and is therefore of significant interest for modeling. However, the stochastic characteristics of early crack development is challenging for model development and validation.
HISTORICAL DOCUMENT. Material requirements for resistance to sulfide stress cracking (SSC) in sour refinery process environments (i.e., environments that contain wet hydrogen sulfide [H2S]). AKA "wet H2S cracking".
CORRECTION OF PUBLICATION:
In January 2016, NACE published an incorrect version of ANSI/NACE MR0103/ISO 17945:2015 (Petroleum, petrochemical and natural gas industries — Metallic materials resistant to sulfide stress cracking in corrosive petroleum refining environments). That document was incorrectly titled ANSI/NACE MR0103/ISO 17495:2016. The erroneous standard was retracted at the time and the NACE Store has the corrected version. NOTE: The contents of both versions of the standard are identical. The only discrepancies are in the title.
The potential for structural alloys to undergo environmentally assisted cracking in molten salts is relatively unexplored due to their limited industrial application. However, fluoride salts are of prime interest to many advanced reactors including the Kairos Power FHR reactors. Table I summarizes literature studies of EAC in molten fluoride salts. For the ten studies shown, seven are for Ni-Mo-Cr family of alloys (INOR-8 / Hastelloy N or variants) that were used in the Molten Salt Reactor Experiment (MSRE), two studies investigate austenitic stainless steels, and there is one report of EAC in oxygen free high conductivity (OFHC) copper.
Different refiners have a variety of procedures in place for hydroprocessing reactor and reactor system shutdowns, depending on the scope of the work to be performed during the downtime. If activities are to be performed inside the reactor (e.g. inspection, maintenance, catalyst changeout, etc.) such that the reactor must be opened to air, shutdowns must include steps to address the various hazards. These same steps must also be applied to associated process equipment related to the reactor system susceptible to similar hazards and damage mechanisms.
Supersonic particle deposition also known as cold dynamic gas spray, or “Cold Spray” is a materials deposition process. During the cold spray process a gas stream, typically helium or nitrogen, is split into two streams where 90% of the gas is sent to an electric heater and 10% is sent to a powder feeder. The powder feeder contains powder composed of small metallic particles, or blends of metallic and non-metallic particles, ranging from 5 to 100 μm in size.
Austenitic stainless steels (SS) are the candidate materials for dry storage canisters. In general, high corrosion resistance is one of the advantageous properties of austenitic stainless steels. However, austenitic stainless steels are susceptible to chloride induced stress corrosion cracking (CISCC) when three criteria are satisfied: susceptible materials, tensile stress and corrosive environments. Dry storage canisters are located at a coastal site in Taiwan, as a result, canisters are exposed to high concentration of moisture and chloride salts under atmospheric environments.
Most of the core internal components of light water reactors (LWRs) are made of austenitic stainless steels (SSs). Exposed to fast neutron irradiation, reactor core internal components are vulnerable to irradiation-induced or irradiation-enhanced degradations. At LWR-relevant temperatures and irradiation doses, significant microstructural and microchemical changes can take place in SSs, leading to deteriorated mechanical and corrosion properties.