Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Survey of Degradation Modes of Candidate Materials for High-level Radioactive Waste Disposal Containers :Final Report
Author: Survey of Degradation Modes of Candidate Materials for High-level Radioactive-waste Disposal Containers
Author: Yucca Mountain Project (U.S.)Publisher:
ISBN:
Category : Corrosion resistant alloys
Languages : en
Pages :
Book Description
These volumes discuss three nickel-based austenitic alloys and three copper-based alloys under consideration for the fabrication of high-level radioactive-waste disposal containers. Literature was surveyed for and the results were applied to the physical, chemical, metallurgical, and mechanical conditions that are expected to occur in the case of the emplaced metal containers at the Yucca Mountain repository.
Survey of the Degradation Modes of Candidate Materials for High-level Radioactive Waste Disposal Containers
Author: D. W. VinsonPublisher:
ISBN:
Category : Corrosion resistant alloys
Languages : en
Pages :
Book Description
Survey of the Degradation Modes of Candidate Materials for High-level Radioactive Waste Disposal Containers
Author: Survey of Degradation Modes of Candidate Materials for High-level Radioactive-waste Disposal Containers
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 71
Book Description
Three iron- to nickel-based austenitic alloys (Types 304L and 316L stainless steels and Alloy 825) are being considered as candidate materials for the fabrication of high-level radioactive-waste containers. Waste will include fuel assemblies from reactors as well as high-level waste in borosilicate glass forms, and will be sent to the prospective repository at Yucca Mountain, Nevada. The decay of radionuclides in the repository will result in the generation of substantial heat and in fluences of gamma radiation. Container materials may undergo any of several modes of degradation in this environment, including atmospheric oxidation; uniform aqueous phase corrosion; pitting; crevice corrosion; sensitization and intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This report is an analysis of data relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of the three austenitic candidate alloys. The candidates are compared in terms of their susceptibilities to these forms of corrosion. Although all three candidates have demonstrated pitting and crevice corrosion in chloride-containing environments, Alloy 825 has the greatest resistance to these types of localized corrosion (LC); such resistance is important because pits can penetrate the metal and serve as crack initiation sites. Both Types 304L and 316L stainless steels are susceptible to SCC in acidic chloride media. In contrast, SCC has not been documented in Alloy 825 under comparable conditions. Gamma radiation has been found to enhance SCC in Types 304 and 304L stainless steels, but it has no detectable effect on the resistance of Alloy 825 to SCC. Furthermore, while the effects of microbiologically induced corrosion have been observed for 300-series stainless steels, nickel-based alloys such as Alloy 825 seem to be immune to such problems. 211 refs., 49 figs., 10 tabs.
Survey of Degradation Modes of Candidate Materials for High-level Radioactive-waste Disposal Containers ; Overview
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 37
Book Description
Three iron- to nickel-based austenitic alloys and three copper-based alloys are being considered as candidate materials for the fabrication of high-level radioactive-waste disposal containers. The austenitic alloys are Types 304L and 316L stainless steels and the high-nickel material Alloy 825. The copper-based alloys are CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). Waste in the forms of both spent fuel assemblies from reactors and borosilicate glass will be sent to the prospective repository at Yucca Mountain, Nevada. The decay of radionuclides will result in the generation of substantial heat and gamma radiation. Container materials may undergo any of several modes of degradation in this environment, including undesirable phase transformations due to a lack of phase stability; atmospheric oxidation; general aqueous corrosion; pitting; crevice corrosion; intergranular stress corrosion cracking; and transgranular stress corrosion cracking. Problems specific to welds, such as hot cracking, may also occur. A survey of the literature has been prepared as part of the process of selecting, from among the candidates, a material that is adequate for repository conditions. The modes of degradation are discussed in detail in the survey to determine which apply to the candidate alloys and the extent to which they may actually occur. The eight volumes of the survey are summarized in Sections 1 through 8 of this overview. The conclusions drawn from the survey are also given in this overview.
Survey of the Degradation Modes of Candidate Materials for High-level Radioactive Waste Disposal Containers. Final Report
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 59
Book Description
One of the most significant factors impacting the performance of waste package container materials under repository relevant conditions is the thermal environment. This environment will be affected by the areal power density of the repository, which is dictated by facility design, and the dominant heat transfer mechanism at the site. The near-field environment will evolve as radioactive decay decreases the thermal output of each waste package. Recent calculations (Buscheck and Nitao, 1994) have addressed the importance of thermal loading conditions on waste package performance at the Yucca Mountain site. If a relatively low repository thermal loading design is employed, the temperature and relative humidity near the waste package may significantly affect the degradation of corrosion allowance barriers due to moist air oxidation and radiolytically enhanced corrosion. The purpose this report is to present a literature review of the potential degradation modes for moderately corrosion resistant nickel copper and nickel based candidate materials that may be applicable as alternate barriers for the ACD systems in the Yucca Mountain environment. This report presents a review of the corrosion of nickel-copper alloys, summaries of experimental evaluations of oxidation and atmospheric corrosion in nickel-copper alloys, views of experimental studies of aqueous corrosion in nickel copper alloys, a brief review of galvanic corrosion effects and a summary of stress corrosion cracking in these alloys.
Survey of the Degradation Modes of Candidate Materials for High-level Radioactive Waste Disposal Containers
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Oxidation and atmospheric corrosion data suggest that addition of Cr provides the greatest improvement in oxidation resistance. Cr-bearing cast irons are resistant to chloride environments and solutions containing strongly oxidizing constituents. Weathering steels, including high content and at least 0.04% Cu, appear to provide adequate resistance to oxidation under temperate conditions. However, data from long-term, high-temperature oxidation studies on weathering steels were not available. From the literature, it appears that the low alloy steels, plain carbon steels, cast steels, and cast irons con-ode at similar rates in an aqueous environment. Alloys containing more than 12% Cr or 36% Ni corrode at a lower rate than plain carbon steels, but pitting may be worse. Short term tests indicate that an alloy of 9Cr-1Mo may result in increased corrosion resistance, however long term data are not available. Austenitic cast irons show the best corrosion resistance. A ranking of total corrosion performance of the materials from most corrosion resistant to least corrosion resistant is: Austenitic Cast Iron; 12% Cr= 36% Ni= 9Cr-1Mo; Carbon Steel= Low Alloy Steels; and Cast Iron. Since the materials to be employed in the Advanced Conceptual Design (ACD) waste package are considered to be corrosion allowance materials, the austenitic cast irons, high Cr steels, high Ni steels and the high Cr-Mo steels should not be considered as candidates for the outer containment barrier. Based upon the oxidation and corrosion data available for carbon steels, low alloy steels, and cast irons, a suitable list of candidate materials for a corrosion allowance outer barrier for an ACD waste package could include, A516, 2.25%Cr -- 1%Mo Steel, and A27.
Degradation Mode Survey Galvanic Corrosion of Candidate Metallic Materials for High-level Radioactive Waste Disposal Containers
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 21
Book Description
This report presents the results of a literature review on galvanic corrosion between candidate metals and alloys currently being considered for the waste package containers.
Degradation Mode Survey Galvanic Corrosion of Candidate Metallic Materials for High-level Radioactive Waste Disposal Containers
Author: Ajit K. RoyPublisher:
ISBN:
Category : Corrosion resistant alloys
Languages : en
Pages : 46
Book Description
This report presents the results of a literature review on galvanic corrosion between candidate metals and alloys currently being considered for the waste package containers.