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in subjects: "Stainless Steel-316L"  
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Structural analysis of a reflux pool-boiler solar receiver

Description: Coupled thermal-structural finite element calculations of a reflux pool-boiler solar receiver were performed to characterize the operating stresses and to address issues affecting the service life of the receiver. Analyses performed using shell elements provided information for receiver material selection and design optimization. Calculations based on linear elastic fracture mechanics principles were performed using continuum elements to assess the vulnerability of a seam-weld to fatigue crack … more
Date: June 1, 1991
Creator: Hoffman, E. L. & Stone, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

WESF cesium capsule behavior at high temperature or during thermal cycling

Description: Double-walled stainless steel (SS) capsules prepared for storage of radioactive /sup 137/Cs from defense waste are now being considered for use as sources for commercial irradiation. Cesium was recovered at B-plant from the high-level radioactive waste generated during processing of defense nuclear fuel. It was then purified, converted to the chloride form, and encapsulated at the Hanford Waste Encapsulation and Storage Facility (WESF). The molten cesium chloride salt was encapsulated by pourin… more
Date: June 1, 1985
Creator: Tingey, G. L.; Gray, W. J.; Shippell, R. J. & Katayama, Y. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Long term laboratory corrosion monitoring of calcine bin set materials exposed to zirconia calcine

Description: Corrosion testing of Type 1025 carbon steel, 405, 304, 304L, 316L, and 347 stainless steels, and 6061-T6 aluminum were conducted in synthetic zirconia calcine to model long term corrosion performance of bin set material. Testing was conducted over a period of 17 years. The existing calcine bin set {number_sign}1 is constructed of Type 405 stainless steel, 2 through 4 are constructed of Type 304 stainless steel and 5 through 7 are constructed of Type 304L stainless steel. The highest rate observ… more
Date: June 1, 1994
Creator: Dirk, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford waste encapsulation: strontium and cesium. [SrF/sub 2/ encapsulated in Hastelloy C-276 and CsCl in stainless steel 316L]

Description: The strontium and cesium fractions separated from high radiation level wastes at Hanford are converted to the solid strontium fluoride and cesium chloride salts, doubly encapsulated, and stored underwater in the Waste Encapsulation and Storage Facility (WESF). A capsule contains approximately 70,000 Ci of /sup 137/Cs or 70,000 to 140,000 Ci of /sup 90/Sr. Materials for fabrication of process equipment and capsules must withstand a combination of corrosive chemicals, high radiation dosages and f… more
Date: June 1, 1976
Creator: Jackson, R. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Description: This volume surveys the effects of welding on the degradation modes of three austenitic alloys: Types 304L and 316L stainless steels and Alloy 825. These materials are candidates for the fabrication of containers for the long-term storage of high-level nuclear waste. The metallurgical characteristics of fusion welds are reviewed here and related to potential degradation modes of the containers. Three specific areas are discussed in depth: (1) decreased resistance to corrosion in the forms of pr… more
Date: June 1, 1988
Creator: Strum, M. J.; Weiss, H.; Farmer, J. C. & Bullen, D. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stress corrosion cracking tests on high-level-waste container materials in simulated tuff repository environments

Description: Types 304L, 316L, and 321 austenitic stainless steel and Incoloy 825 are being considered as candidate container materials for emplacing high-level waste in a tuff repository. The stress corrosion cracking susceptibility of these materials under simulated tuff repository conditions was evaluated by using the notched C-ring method. The tests were conducted in boiling synthetic groundwater as well as in the steam/air phase above the boiling solutions. All specimens were in contact with crushed To… more
Date: June 1, 1986
Creator: Abraham, T.; Jain, H. & Soo, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Electrochemical determination of the corrosion behavior of candidate alloys proposed for containment of high level nuclear waste in tuff

Description: Long-term geological disposal of nuclear waste requires corrosion-resistant canister materials for encapsulation. Several austenitic stainless steels are under consideration for such purposes for the disposal of high-level waste at the candidate repository site located at Yucca Mountain, Nevada. With regard to corrosion considerations, a worst case scenario at this prospective repository location would result from the intrusion of vadose water. This preliminary study focuses on the electrochemi… more
Date: June 18, 1984
Creator: Glass, R.S.; Overturf, G.E.; Garrison, R.E. & McCright, R.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An Analysis of Burst Disc Pressure Instability

Description: During the development stage of the 1X Acorn burst disc, burst pressure test results exhibited an unexpected increase of 8 to 14% over times of 90--100 days from initial fabrication. This increase is a concern where design constraints require stability. The disc material, 316L stainless steel sheet, is formed to a dome-like geometry and scored to produce a thin-walled, high-strength ligament. The fracture events controlling burst occur in that ligament. Thus it has been characterized both for t… more
Date: June 1, 2000
Creator: Robinson, S. L.; B. C. Odegard, Jr.; Moody, N. r. & Goods, S. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Yucca Mountain project container fabrication, closure and non-destructive evaluation development activities; Summary and viewgraphs

Description: In this presentation, container fabrication, closure, and non-destructive evaluation (NDE) process development activities are described. All of these activities are interrelated, and will contribute to the metal barrier selection activity. The plan is to use a corrosion-resistant material in the form of a cylinder with a wall thickness of {approximately}1cm (2cm for pure copper.) The materials under consideration include the three austenitic alloys: stainless steel-304L, stainless steel-316L an… more
Date: June 1989
Creator: Russell, E. W. & Nelson, T. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Stress corrosion cracking of candidate waste container materials; Final report

Description: Six alloys have been selected as candidate container materials for the storage of high-level nuclear waste at the proposed Yucca mountain site in Nevada. These materials are Type 304L stainless steel (SS). Type 316L SS, Incoloy 825, phosphorus-deoxidized Cu, Cu-30%Ni, and Cu-7%Al. The present program has been initiated to determine whether any of these materials can survive for 300 years in the site environment without developing through-wall stress corrosion cracks. and to assess the relative … more
Date: June 1, 1992
Creator: Park, J. Y.; Maiya, P. S.; Soppet, W. K.; Diercks, D. R.; Shack, W. J. & Kassner, T. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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