Menu
Search
Filters
Close
Menu

Save 20% on select titles with code HIDDEN24 - Shop The Sale Now

Review Of Techniques To Evaluate SCC Susceptibility Of Carbon Steels Used In Construction Of Nuclear Waste Tanks

Review of Techniques to Evaluate SCC Susceptibility of Carbon Steels Used in Construction of Hanford Nuclear Reservation Waste Tanks
Available for download

The Hanford Nuclear Reservation contains radioactive and chemically hazardous wastes arising mostly from weapons production, beginning with World War II and continuing through the Cold War. The wastes are stored in 177 carbon steel underground storage tanks, of which 149 are single-shell tanks (SSTs) and the remaining are double-shell tanks (DSTs). The U.S. Department of Energy, Office of River Protection is responsible for retrieving the tank wastes, treating them in order to encapsulate them in glass logs, and then permanently closing the tanks and associated facilities.

Product Number: 51322-18062-SG
Author: B.C. Rollins, S. Chawla, J. Gerst, J.A. Beavers, J. Page, C. Girardot, S. Campbell, N. Sridhar
Publication Date: 2022
Industries: Corrosion Monitoring and Control , Coatings
$0.00
$20.00
$20.00

Stress corrosion cracking (SCC) is a documented threat to the integrity of carbon steel radioactive waste storage tanks at the Hanford Nuclear Reservation site. Presently, the slow strain rate (SSR) test is the workhorse test technique used for assessing SCC of carbon steels in nuclear waste simulants. The main advantages of the standard SSR technique are that it is relatively rapid, sensitive in detecting SCC, and relatively inexpensive. SSR test results are typically classified as “SCC” or “No SCC”, depending on the ductility parameters from the test and observations of crack features. Occasionally, tests are not easily classified, which results in a third category, “Inconclusive”. Inconclusive results are usually related to variations in ductility parameters compared to the control specimen, or the presence of atypical fracture facets or secondary features on the gage section. Regardless of the cause of the inconclusive result, these tests create uncertainty in assessing susceptibility to SCC. This paper describes the results of a preliminary study undertaken to develop an SCC testing protocol for evaluating inconclusive results. Three alternatives to the standard SSR technique, slower SSR (reduced extension rate), Ripple SSR, and notched SSR, were evaluated. Additionally, SCC evaluations from a crack growth technique using a compact tension specimen were compared to the results of the alternative SSR methods. The study showed that, regardless of the technique evaluated, there will be inconclusive results due to subjective aspects of the post-test evaluation. However, there appears to be a critical potential below which SCC is absent. The value of this potential varies with the test method.  

Stress corrosion cracking (SCC) is a documented threat to the integrity of carbon steel radioactive waste storage tanks at the Hanford Nuclear Reservation site. Presently, the slow strain rate (SSR) test is the workhorse test technique used for assessing SCC of carbon steels in nuclear waste simulants. The main advantages of the standard SSR technique are that it is relatively rapid, sensitive in detecting SCC, and relatively inexpensive. SSR test results are typically classified as “SCC” or “No SCC”, depending on the ductility parameters from the test and observations of crack features. Occasionally, tests are not easily classified, which results in a third category, “Inconclusive”. Inconclusive results are usually related to variations in ductility parameters compared to the control specimen, or the presence of atypical fracture facets or secondary features on the gage section. Regardless of the cause of the inconclusive result, these tests create uncertainty in assessing susceptibility to SCC. This paper describes the results of a preliminary study undertaken to develop an SCC testing protocol for evaluating inconclusive results. Three alternatives to the standard SSR technique, slower SSR (reduced extension rate), Ripple SSR, and notched SSR, were evaluated. Additionally, SCC evaluations from a crack growth technique using a compact tension specimen were compared to the results of the alternative SSR methods. The study showed that, regardless of the technique evaluated, there will be inconclusive results due to subjective aspects of the post-test evaluation. However, there appears to be a critical potential below which SCC is absent. The value of this potential varies with the test method.  

Product tags
Also Purchased
Picture for Methods of Monitoring Reinforced Concrete Corrosion in Formulations for Nuclear Facilities
Available for download

Methods of Monitoring Reinforced Concrete Corrosion in Formulations for Nuclear Facilities

Product Number: 51317--9154-SG
ISBN: 9154 2017 CP
Author: Damián Vazquez
Publication Date: 2017
$20.00

Two concrete formulations, one of ordinary portland cement and one of pozzolanic portland cement, are compared by rebar corrosion criteria. Both formulations are candidates for nuclear applications whose durability requirement is higher than 300 years.
Picture for Rethinking Sulfide Stress Cracking (SSC) Resistance Super Martensitic Stainless Steel (SMSS-13Cr) Bar Stock With 95 Ksi MY
Available for download

Rethinking Sulfide Stress Cracking (SSC) Resistance Super Martensitic Stainless Steel (SMSS-13Cr) Bar Stock With 95 Ksi MY

Product Number: 51322-17614-SG
Author: Karthik Krishnan, Chad Glaesman
Publication Date: 2022
$20.00

13Cr-5Ni-2Mo type Super Martensitic stainless steels referred to as SMSS-13Cr type grades can provide good general corrosion resistance such as in high CO2 environments combined with higher strengths and excellent toughness2 making them a prospective material choice for long term downhole completion equipment depending on actual well conditions. One of the main limiting factors for the use of SMSS-13Cr type grades is the Sulfide Stress Cracking (SSC) resistance in presence of H2S in downhole well conditions. Therefore, a good understanding of this behavior is essential to facilitate the material selection process. 
Picture for Revisiting The Anodic Dissolution Of Pure Iron In Strong Acid: Replication Of Bockris’ Estimation Of Butler-Volmer
Available for download

Revisiting The Anodic Dissolution Of Pure Iron In Strong Acid: Replication Of Bockris’ Estimation Of Butler-Volmer

Product Number: 51322-17681-SG
Author: Mohiedin Bagheri Hariri, Bruce Brown, Srdjan Nesic
Publication Date: 2022
$20.00

Reviewing literature related to corrosion research brings to light the importance of understanding the mechanisms involved, and how this is essential to aid in development of mathematical models for corrosion prediction. The current research documents possible mechanisms for the dissolution of pure iron in strong acid in a potential range in the potential range of ±50 mV vs. OCP, providing explanations for corrosion engineers and researchers working with mild steel. Prediction of corrosion rate relies on the precise understanding of the anodic and cathodic processes at the metal surface in the potential range close to the OCP.
Categories
Industry
Recently viewed
Popular tags
View all

Association for Materials Protection and Performance

© AMPP All Rights Reserved.
Membership Terms of Content Use
Contact Customer Support