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Metallurgical analysis of a 304L stainless steel canister from the Spent Fuel Test - Climax

Description: Results of a metallurgical examination of a type 304L stainless steel canister that had been used to store spent nuclear fuel in an underground granite formation for about three years are reported. No observable corrosion or cracking were found. The results are applied to waste packages in a potential high level nuclear waste repository in tuff. 10 refs., 9 figs., 2 tabs.
Date: April 23, 1985
Creator: Weiss, H.; Van Konynenburg, R.A. & McCright, R.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Residual stresses due to processing of composite tubes

Description: X-ray and neutron diffraction were used to characterize residual stresses in composite tubing of a corrosion-resistant clad alloy on carbon steel. A useful X-ray method, based on the measurement of the fcc (3 1 1) reflection using Cr K{sub {beta}} radiation, was developed which allowed precise determination of surface residual stresses in the textured clad layer. Neutron diffraction measurements were carried out in both the carbon steel core and the clad layer, using the bcc (2 1 1) and fcc (3 … more
Date: February 5, 1998
Creator: Wang, X. L.; Hubbard, C. R.; Spooner, S.; Taljat, B. & Keiser, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Overview of low temperature sensitization

Description: A review of the literature on low temperature sensitization (LTS) has been conducted to determine if LTS-related microstructural changes can occur in Type 304L stainless steel within the times and temperatures associated with nuclear waste storage. It was found that Type 304L stainless steel is susceptible to sensitization and LTS, and that cold work plays an important role in determining the rate of LTS. Severely cold worked Type 304L stainless steel would clearly develop LTS-related microstru… more
Date: December 1, 1983
Creator: Fox, M.J. & McCright, R.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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On the interface between LENS deposited stainless steel 304L repair geometry and cast or machined components.

Description: Laser Engineered Net Shaping (LENS) is being evaluated for use as a metal component repair/modification process for the NWC. An aspect of the evaluation is to better understand the characteristics of the interface between LENS deposited material and the substrate on which it is deposited. A processing and metallurgical evaluation was made on LENS processed material fabricated for component qualification tests. A process parameter evaluation was used to determine optimum build parameters and the… more
Date: December 1, 2004
Creator: Smugeresky, John E.; Harris, Marc F.; Griffith, Michelle Lynn; Gill, David Dennis & Robino, Charles Victor
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Temperature and strain-rate effects on deformation mechanisms in irradiated stainless steel

Description: Analysis of the deformation microstructures in ion-irradiated stainless steel shows twinning to be the predominant deformation mode at room temperature. Dislocation channelling also occurs under slow strain rate conditions. Stresses required for twinning were calculated by the model of Venables and are compatible with observed yield stresses in neutron-irradiated material if loops are the principal twin source. Computation of the expected radiation hardening from the defect structure, based on … more
Date: November 1, 1994
Creator: Brimhall, J. L.; Cole, J. I.; Vetrano, J. S. & Bruemmer, S. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radiation-induced instability of MnS precipitates and its possible consequences on irradiation-induced stress corrosion cracking of austenitic stainless steels

Description: Irradiation-assisted stress corrosion cracking (IASCC) is a significant materials issue for the light water reactor (LWR) industry and may also pose a problem for fusion power reactors that will use water as coolant. A new metallurgical process is proposed that involves the radiation-induced release into solution of minor impurity elements not usually thought to participate in IASCC. MnS-type precipitates, which contain most of the sulfur in stainless steels, are thought to be unstable under ir… more
Date: December 1, 1996
Creator: Chung, H. M.; Sanecki, J. E. & Garner, F. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Preliminary lifetime predictions for 304 stainless steel as the LANL ABC blanket material

Description: The prediction of materials lifetime in the preconceptual Los Alamos National Laboratory (LANL) Accelerator-Based Conversion of Plutonium (ABC) is of utmost interest. Because Hastelloy N showed good corrosion resistance to the Oak Ridge National Laboratory Molten Salt Reactor Experiment fuel salt that is similar to the LANL ABC fuel salt, Hastelloy N was originally proposed for the LANL ABC blanket material. In this paper, the possibility of using 304 stainless steel as a replacement for the Ha… more
Date: November 1, 1997
Creator: Park, J. J.; Buksa, J. J.; Houts, M. G. & Arthur, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Materials property testing using a stress-strain microprobe

Description: The Stress-Strain Microprobe (SSM) uses an automated ball indentation technique to obtain flow data from a localized region of a test specimen or component. This technique is used to rapidly determine the yield strength and microstructural condition of a variety of materials including pressure vessel steels, stainless steels, and nickel-base alloys. The SSM provides an essentially non-destructive technique for the measurement of yield strength data. This technique is especially suitable for the… more
Date: September 1, 1998
Creator: Panayotou, N.F.; Baldrey, D.G. & Haggag, F.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pulsed ion beam surface treatment for preparing rapidly solidified corrosion resistant steel and aluminum surfaces

Description: Intense, pulsed ion beams were used to melt and rapidly resolidify Types 316F, 316L and sensitized 304 stainless steel surfaces to eliminate the negative effects of microstructural heterogeneity on localized corrosion resistance. Anodic polarization curves determined for 316F and 316L showed that passive current densities were reduced and pitting potentials were increased due to ion beam treatment. Type 304 samples sensitized at 600 C for 100 h showed no evidence of grain boundary attack when s… more
Date: March 1, 1995
Creator: Buchheit, R. G.; Maestas, L. M.; McIntyre, D. C.; Stinnett, R. W. & Greenly, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of LWR coolant environments on fatigue lives of austenitic stainless steels

Description: The ASME Boiler and Pressure Vessel Code fatigue design curves for structural materials do not explicitly address the effects of reactor coolant environments on fatigue life. Recent test data indicate a significant decrease in fatigue life of pressure vessel and piping materials in light water reactor (LWR) environments. Fatigue tests have been conducted on Types 304 and 316NG stainless steel in air and LWR environments to evaluate the effects of various material and loading variables, e.g., st… more
Date: July 1997
Creator: Chopra, O. K. & Gavenda, D. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of fluoride and other halogen ions on the external stress corrosion cracking of Type 304 austenitic stainless steel

Description: The drip procedure from the Standard Test Method for Evaluating the Influence of Thermal Insulation on External Stress Corrosion Cracking Tendency of Austenitic Stainless Steel (ASTM C 692-95a) was used to research the effect of halogens and inhibitors on the External Stress Corrosion Cracking (ESCC) of Type 304 stainless steel as it applies to Nuclear Regulatory Commission Regulatory Guide 1.36, Nonmetallic Thermal Insulation for Austenitic Stainless Steel. The solutions used in this research … more
Date: July 1, 1997
Creator: Whorlow, K. M. & Hutto, F. B., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion in ICPP fuel storage basins

Description: The Idaho Chemical Processing Plant currently stores irradiated nuclear fuel in fuel storage basins. Historically, fuel has been stored for over 30 years. During the 1970`s, an algae problem occurred which required higher levels of chemical treatment of the basin water to maintain visibility for fuel storage operations. This treatment led to higher levels of chlorides than seen previously which cause increased corrosion of aluminum and carbon steel, but has had little effect on the stainless st… more
Date: September 1, 1993
Creator: Dirk, W.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Remote reactor repair: GTA (gas tungsten Arc) weld cracking caused by entrapped helium

Description: A repair patch was welded to the wall of a nuclear reactor tank using remotely controlled thirty-foot long robot arms. Further repair was halted when gas tungsten arc (GTA) welds joining type 304L stainless steel patches to the 304 stainless steel wall developed toe cracks in the heat-affected zone (HAZ). The role of helium in cracking was investigated using material with entrapped helium from tritium decay. As a result of this investigation, and of an extensive array of diagnostic tests perfor… more
Date: January 1, 1988
Creator: Kanne, W. R., Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Parametric effects of glass reaction under unsaturated conditions

Description: Eventual liquid water contact of high-level waste glass stored under the unsaturated conditions anticipated at the Yucca Mountain site will be by slow intrusion of water into a breached container/canister assembly. The water flow patterns under these unsaturated conditions will vary, and the Unsaturated Test method has been developed by the YMP to study glass reaction. The results from seven different sets of tests done to investigate the effect of systematically varying parameters, such as gla… more
Date: November 1, 1989
Creator: Bates, J.K.; Gerding, T.J. & Woodland, A.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermal analysis of the horizontal shipping container for normal conditions of transport with solar insolation

Description: A thermal analysis of the horizontal shipping container (HSC) was performed to determine the temperatures at the outer surface of the inner container during normal conditions of transport with incident solar radiation. There are two methods by which this analysis can be performed: (1) it can be run as a steady-state problem where it is assumed that the incident solar radiation is applied to the package 24 hours per day, or (2) it can be run as a cyclic transient problem where the incident solar… more
Date: April 2, 1993
Creator: Stumpfl, E.; Feldman, M. R. & Anderson, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Residual stresses and stress corrosion cracking in pipe fittings

Description: Residual stresses can play a key role in the SCC performance of susceptible materials in PWR primary water applications. Residual stresses are stresses stored within the metal that develop during deformation and persist in the absence of external forces or temperature gradients. Sources of residual stresses in pipe fittings include fabrication processes, installation and welding. There are a number of methods to characterize the magnitude and orientation of residual stresses. These include nume… more
Date: June 1, 1994
Creator: Parrington, R.J.; Scott, J.J. & Torres, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Causes and solutions for cracking of coextruded and weld overlay floor tubes in black liquor recovery boilers

Description: Cracking of coextruded, black liquor recovery boiler floor tubes is both a safety and an economic issue to mill operators. In an effort to determine the cause of the cracking and to identify a solution, extensive studies, described in this and three accompanying papers, are being conducted. In this paper, results of studies to characterize both the cracking and the chemical and thermal environment are reported. Based on the results described in this series of papers, a possible mechanism is pre… more
Date: September 1, 1998
Creator: Keiser, J. R.; Taljat, B. & Wang, X. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Experimental determination of residual stress by neutron diffraction in a boiling water reactor core shroud

Description: Residual strains in a 51 mm (2-inch) thick 304L stainless steel plate have been measured by neutron diffraction and interpreted in terms of residual stress. The plate, measuring (300 mm) in area, was removed from a 6m (20-ft.) diameter unirradiated boiling water reactor core shroud, and included a multiple-pass horizontal weld which joined two of the cylindrical shells which comprise the core shroud. Residual stress mapping was undertaken in the heat affected zone, concentrating on the outside … more
Date: June 1, 1996
Creator: Payzant, A.; Spooner, S.; Zhu, Xiaojing & Hubbard, C.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scenarios for the Evaluation of the Criticality Potential of High Actinide Glasses

Description: Vitrification is one of the leading options for immobilization of actinide-containing materials no longer needed for national defense. For these glasses to be suitable for disposal, it must be established that a significant potential for a nuclear criticality involving these glasses does not exist. The vitrification working group within the nuclear materials disposition program has been given the responsibility for developing scenarios to be evaluated. In this report, potential bounding scenari… more
Date: January 19, 1996
Creator: Plodinec, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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