Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 19
Book Description
Understanding the Risk of Chloride Induced Stress Corrosion Cracking of Interim Storage Containers for the Dry Storage of Spent Nuclear Fuel
Author: Understanding the Risk of Chloride Induced Stress Corrosion Cracking of Interim Storage Containers for the Dry Storage of Spent Nuclear Fuel
Author: Understanding the Risk of Chloride Induced Stress Corrosion Cracking
Author: Chloride-induced Stress Corrosion Cracking in Used Nuclear Fuel Welded Stainless Steel Canisters
Author: Yi XiePublisher:
ISBN:
Category :
Languages : en
Pages : 159
Book Description
The used nuclear fuel (UNF) dry storage is one of the options for the interim storage of UNF. Most of the dry storages are located in coastal and lake/river-side regions. They are designed to serve for 60 years or even more. In most cases, the storage canister which is in a welded austenitic stainless steel (SS) structure will be exposed to a salt-containing environment for the entire storage period. Since the canister is a primary barrier to fission product release, it has been determined to be robust with little degradation due to thermal, mechanical or radiation effects. However, atmospheric and aqueous pitting corrosion, as well as chloride induced stress corrosion cracking (CISCC) may occur because of the aggressive species that form on or contact the canister surface and the residual tensile stresses. The objective of this dissertation is to develop an experimental integrated approach to study the fundamentals of CISCC of Type 304L base metal (BM) and weld metal (WM) and collect data to evaluate CISCC under relevant environmental conditions, and to develop a model based on probabilistic analysis by parameterizing and validating using the experimental studies to predict long-term pitting behaviors of the storage canister. The efforts and findings documented in this dissertation consist of: (1) The electrochemical techniques are used to identify the corrosion potential, passive current, pitting potential, passivation layer impedance of the BM and WM immersed in highly concentrated chloride solutions at 40 and 70 °C. (2) The pitting corrosion resistance in the chloride-containing aqueous and atmospheric environment is evaluated and compared by the pit density and frequency distribution of depth. It is found that the welding process depresses the corrosion resistance of a metal matrix under the investigated environments. Metastable pitting is distinct especially for the early exposure times. The pitting corrosion resistance is influenced by the chloride concentration and the temperature. The findings of pitting corrosion in humid environments provide better forecasting on actual in-service canisters. (3) CISCC experiments with in situ measurement of crack growth rates of the BM and WM exposed to the salt deposit humid environment (15% RH at 70 °C) are conducted in the SCC test system. The WM has much higher SCC growth rate than the BM even with lower applied stress intensity, indicating the SCC resistance of the steel is depressed by the welding process. (4) Micro-characteristics imaging and analytical facilities are used to analyze the microstructure of pitting corrosion and CISCC. (5) The experimental results are used to concurrently parameterize and validate the model based on probabilistic analysis for pitting corrosion. The concept of Markov chain, as well as the pitting corrosion mechanism, is involved in this model to predict the pitting corrosion states, density and depth. Since the safety performance of the storage is major concerned in the nuclear industry, this study provides a technical basis for evaluating the technical issue and supports the development of evaluating SCC occurrence, crack depth and growth rate on in-service storage canisters.
Stress Corrosion Cracking of Spent Nuclear Fuel Interim Storage Containers
Author: Advances in Materials Science for Environmental and Energy Technologies VI
Author: Tatsuki OhjiPublisher: John Wiley & Sons
ISBN: 1119455405
Category : Technology & Engineering
Languages : en
Pages : 283
Book Description
An excellent one-volume resource for understanding the most important current issues in the research and advances in materials science for environmental and energy technologies This proceedings volume contains a collection of 20 papers from the 2016 Materials Science and Technology (MS&T'16) meeting held in Salt Lake City, UT, from October 24-27 of that year. These conference symposia provided a forum for scientists, engineers, and technologists to discuss and exchange state-of-the-art ideas, information, and technology on advanced methods and approaches for processing, synthesis, characterization, and applications of ceramics, glasses, and composites. Topics covered include: the 8th International Symposium on Green and Sustainable Technologies for Materials Manufacturing Processing; Materials Issues in Nuclear Waste Management in the 21st Century; Construction and Building Materials for a Better Environment; Materials for Nuclear Applications and Extreme Environments; Nanotechnology for Energy, Healthcare, and Industry; and Materials for Processes for CO2 Capture, Conversion and Sequestration. Logically organized and carefully selected articles give insight into advances in materials science for environmental and energy technologies. Incorporates the latest developments related to advances in materials science for environmental and energy technologies Advances in Materials Science for Environmental and Energy Technologies VI: Ceramic Transactions Volume 262 is ideal for academics in mechanical and chemical engineering, materials and or ceramics, chemistry departments and for those working in government laboratories.
Potential Chloride-induced Stress Corrosion Cracking of Austenitic Stainless Steel and Maintenance of Dry Storage Casks System Canisters
Author: Publisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 6
Book Description
Fuel Canister Stress Corrosion Cracking Susceptibility Experimental Results
Author: Colleen Shelton-DavisPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The National Spent Nuclear Fuel Program is tasked with ensuring the U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) is acceptable for permanent disposal at a designated repository. From a repository acceptance criteria viewpoint and from a transportation viewpoint, of significant concern is the condition of the container at the time of shipment. Because the fuel will be in temporary storage for as much as 50 years, verification that no significant degradation has occurred to the canister is required to preclude repackaging all the fuel. Many canisters are also being removed from wet storage, vacuum dried (hot or cold), and then placed into dry storage. This process could have a detrimental effecton canister integrity. Research is currently underway to provide a technically sound assessment of the expected canister condition at the end of interim storage.
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