Corrosion and Deposits from Combustion of Solid Waste—Part VII: Coincineration of Refuse and Sewage Sludge

1980 ◽  
Vol 102 (3) ◽  
pp. 698-705 ◽  
Author(s):  
H. H. Krause ◽  
P. W. Cover ◽  
W. E. Berry ◽  
R. A. Olexsey
Keyword(s):  
Sewage Sludge ◽  
Stainless Steels ◽  
Cost Effective ◽  
Metal Temperature ◽  
Low Alloy Steels ◽  
Gas Temperature ◽  
Corrosion Rates ◽  
Prevention Measure ◽  
Alloy Steels ◽  
Municipal Refuse

Corrosion probe exposures were conducted in the Harrisburg, Pennsylvania, incinerator to determine the effects of burning low-chloride sewage sludge with municipal refuse. Probes having controlled temperature gradients were used to measure corrosion rates for exposure times up to 816 hours. The effects of exposure time, metal temperature, and gas temperature were studied. The results demonstrated that the addition of the sludge reduced the initial corrosion rates of carbon and low-alloy steels to about half that from refuse alone. Little effect was observed on the rates for Types 310 and 347 stainless steels. An aluminized coating on steel resisted corrosion effectively and offers promise as a cost-effective substitute for expensive alloys. In the range 500–900° F the corrosion rates of carbon steel and T22 increased with temperature while those for the stainless steels decreased. Reducing the flue gas temperature from 1500° F to 1100° F reduced corrosion rates significantly and made them less dependent on metal temperature. The addition of low-chloride sludge to refuse is recommended as a corrosion prevention measure and a waste disposal technique.

Corrosion of Carbon and Low-Alloy Steels In Out-of-Pile Boiling-Water-Reactor Environment

CORROSION ◽  
1961 ◽  
Vol 17 (6) ◽  
pp. 269t-276t ◽  
Author(s):  
D. C. VREELAND ◽  
G. G. GAUL ◽  
W. L PEARL
Keyword(s):  
Stainless Steels ◽  
Dynamic Test ◽  
Boiling Water ◽  
Saturated Steam ◽  
Boiling Water Reactor ◽  
Low Alloy Steels ◽  
Water Reactor ◽  
High Ph ◽  
Corrosion Rates ◽  
Alloy Steels

Abstract Results are reported of extensive corrosion testing of carbon and low-alloy steels in a dynamic test loop simulating the various environments found in a nuclear boiling-water-reactor system. Quantitative data and metallographic and visual observations of specimens tested in saturated steam, saturated water and a steam-water mixture, all at 545 F and 1000 psi are presented. Water and steam conditions are based on 10 to 20 ppm oxygen in the steam with a 1:8 stoichiometric ratio of hydrogen to oxygen, a condition representative of the hydrogen and oxygen formed in a boiling-water reactor from radiolytic water decomposition. The water is maintained at pH 7, high purity with no other additives. A description of the boiling-water dynamic-test facilities and operating procedures is included. Total corrosion and corrosion product released into the system is measured. No appreciable difference was noted among corrosion rates of carbon steels, high-strength low-alloy steels and alloy steels studied, although all showed higher rates than the AISI Type 300 series stainless steels tested. Comparisons also were made with other stainless steels. No selective attack was noted on welded specimens. Corrosion rates obtained on the carbon and low-alloy steels are lower than those obtained by other investigators on similar materials in test loops simulating pressurized water-reactor systems operated at high pH (> 10) with only hydrogen gas in the water. The iron-to-system rates in the present tests were appreciably lower than those in similar tests in high pH and neutral pH systems with a hydrogen environment. 8.4.5, 6.2.3, 6.2.4

AK STEEL 409 Ni

Alloy Digest ◽  
2021 ◽  
Vol 70 (6) ◽  
Keyword(s):  
Stainless Steel ◽  
Corrosion Resistance ◽  
Physical Properties ◽  
Cost Effective ◽  
Heat Treating ◽  
Low Alloy Steels ◽  
Service Temperature ◽  
Alloy Steels ◽  
Cost Effective Alternative ◽  
Maximum Service Temperature

Abstract AK Steel 409 Ni is a 11% chromium ferritic stainless steel microalloyed with titanium and nickel. It provides excellent weldability, toughness, and fabricating characteristics superior to those of type 409 stainless steel in thicknesses over 3.05 mm (0.120 in.). This alloy is a cost effective alternative to mild steels and low-alloy steels that also provides superior corrosion and/or oxidation resistance. The recommended maximum service temperature of AK Steel 409 Ni is 730 °C (1350 °F). This datasheet provides information on composition, physical properties, elasticity, and tensile properties. It also includes information on corrosion resistance as well as heat treating and joining. Filing Code: SS-1336. Producer or source: AK Steel Corporation.

Development of New Design Fatigue Curves in Japan: Proposal of a New Fatigue Evaluation Method

2018 ◽  
Author(s):  
Seiji Asada ◽  
Akihiko Hirano ◽  
Toshiyuki Saito ◽  
Yasukazu Takada ◽  
Hideo Kobayashi
Keyword(s):  
Stainless Steels ◽  
Evaluation Method ◽  
Austenitic Stainless Steels ◽  
Fatigue Tests ◽  
Carbon Steels ◽  
Low Alloy Steels ◽  
Stress Effect ◽  
Fatigue Data ◽  
Alloy Steels ◽  
Fatigue Evaluation

In order to develop new design fatigue curves for carbon steels & low-alloy steels and austenitic stainless steels and a new design fatigue evaluation method that are rational and have clear design basis, Design Fatigue Curve (DFC) Phase 1 subcommittee and Phase 2 subcommittee were established in the Atomic Energy Research Committee in the Japan Welding Engineering Society (JWES). The study on design fatigue curves was actively performed in the subcommittees. In the subcommittees, domestic and foreign fatigue data of small test specimens in air were collected and a comprehensive fatigue database (≈6000 data) was constructed and the accurate best-fit curves of carbon steels & low-alloy steels and austenitic stainless steels were developed. Design factors were investigated. Also, a Japanese utility collaborative project performed large scale fatigue tests using austenitic stainless steel piping and low-alloy steel flat plates as well as fatigue tests using small specimens to obtain not only basic data but also fatigue data of mean stress effect, surface finish effect and size effect. Those test results were provided to the subcommittee and utilized the above studies. Based on the above studies, a new fatigue evaluation method has been developed.

Proposal of Fatigue Life Equations for Carbon and Low-Alloy Steels and Austenitic Stainless Steels as a Function of Tensile Strength

2013 ◽  
Author(s):  
Hiroshi Kanasaki ◽  
Makoto Higuchi ◽  
Seiji Asada ◽  
Munehiro Yasuda ◽  
Takehiko Sera
Keyword(s):  
Tensile Strength ◽  
Fatigue Life ◽  
Stainless Steels ◽  
Room Temperature ◽  
Austenitic Stainless Steels ◽  
Low Alloy Steels ◽  
Strength Based ◽  
Fatigue Data ◽  
Current Design ◽  
Alloy Steels

Fatigue life equations for carbon & low-alloy steels and also austenitic stainless steels are proposed as a function of their tensile strength based on large number of fatigue data tested in air at RT to high temperature. The proposed equations give a very good estimation of fatigue life for the steels of varying tensile strength. These results indicate that the current design fatigue curves may be overly conservative at the tensile strength level of 550 MPa for carbon & low-alloy steels. As for austenitic stainless steels, the proposed fatigue life equation is applicable at room temperature to 430 °C and gives more accurate prediction compared to the previously proposed equation which is not function of temperature and tensile strength.

Corrosion of Martensitic Stainless Steel Weldments

2006 ◽  
pp. 115-124
Keyword(s):  
Corrosion Resistance ◽  
Stainless Steels ◽  
Low Alloy Steels ◽  
Martensitic Stainless Steels ◽  
Tetragonal Crystal ◽  
Tetragonal Crystal Structure ◽  
Hydrogen Induced Cracking ◽  
Stress Corrosion Resistance ◽  
Sulfide Stress ◽  
Alloy Steels

Abstract Martensitic stainless steels are essentially iron-chromium-carbon alloys that possess a body-centered tetragonal crystal structure (martensitic) in the hardened condition. Martensitic stainless steels are similar to plain carbon or low-alloy steels that are austenitized, hardened by quenching, and then tempered for increased ductility and toughness. This chapter provides a basic understanding of grade designations, properties, corrosion resistance, and general welding considerations of martensitic stainless steels. It also discusses the causes for hydrogen-induced cracking in martensitic stainless steels and describes sulfide stress corrosion resistance of type 410 weldments.

Use of NUREG/CR-6909 Environmentally-Assisted Fatigue Rules for a Nuclear Plant License Renewal Application

2011 ◽  
Author(s):  
William F. Weitze ◽  
Matthew C. Walter ◽  
Keith R. Evon
Keyword(s):  
Stainless Steels ◽  
Water Environment ◽  
Austenitic Stainless Steels ◽  
Nuclear Regulatory Commission ◽  
The United States ◽  
Nuclear Plant ◽  
Lessons Learned ◽  
Low Alloy Steels ◽  
Alloy Steels ◽  
Regulatory Commission

As part of the process of renewing the operating license for an additional 20 years after the original 40-year design life, nuclear plant owners in the United States (US) are required to show that they are managing the effects of aging of systems, structures, and components. US Nuclear Regulatory Commission (NRC) report NUREG-1801, the “Generic Aging Lessons Learned (GALL) Report,” identifies acceptable aging management programs, including programs for fatigue and cyclic operation. This includes fatigue usage analyses that account for reduced fatigue life for components in a reactor water environment. Earlier revisions of the GALL report required plants to perform environmentally-assisted fatigue (EAF) analyses using the rules in reports NUREG/CR-6583 (for carbon and low alloy steels) and NUREG/CR-5704 (for austenitic stainless steels), which were developed in 1998 and 1999, respectively. However, GALL Revision 2, issued in December 2010, requires that the rules in NUREG/CR-6909, issued in 2007, be used for nickel alloy materials, and allows it to be used for carbon, low-alloy and stainless steels as an alternative to those in the previous reports. This paper presents an application of the NUREG/CR-6909 rules, and makes several observations about the differences between using the newer and older rules. The analyses presented were performed for a sample set of boiling water reactor (BWR) locations.

A Consideration of Margin on Fatigue Design Curves for Carbon and Low-Alloy Steels

2011 ◽  
Author(s):  
Makoto Higuchi ◽  
Masahiro Takanashi ◽  
Ichiro Tamura ◽  
Toshiaki Takada
Keyword(s):  
Stainless Steels ◽  
Fatigue Curve ◽  
Light Water Reactor ◽  
Ferritic Steels ◽  
Low Alloy Steels ◽  
Light Water ◽  
Fatigue Design ◽  
The Us ◽  
Asme Code ◽  
Alloy Steels

In 2007, the US NRC issued Regulatory Guide 1.207[1] and NUREG/CR-6909[2] for evaluating fatigue incorporating the life reduction due to the effects of light-water reactor environment for new reactors. NUREG/CR-6909 provides new design fatigue curves (DFC) for carbon, low-alloy and stainless steels which are different from those in the ASME Boiler and Pressure Vessel Code Section III[3] (2007 Edition). The design fatigue curves for carbon and low-alloy steels in NUREG/CR-6909 are higher than that for ferritic steels of which specified minimum tensile strength is 552 MPa (80 ksi) or less in the ASME Code Section III. The design fatigue curve for stainless steel in the ASME Code Section III was changed to the same curve as NUREG/CR-6909 in the 2009 Addenda. However, those for carbon and low-alloy steels are still different from the NUREG curves.

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