565 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Metallography"  
prev Results: 505 - 528 next
open access

TMI-2 Vessel Investigation Project (VIP) Metallurgical Program

Description: The TMI-2 Vessel Investigation Project (VIP) Metallurgical Program is a part of the international TMI-2 Vessel Investigation Project being conducting jointly by the US Nuclear Regulatory Commission and the Organization for Economic Co-operation and Development (OECD). The overall project consists of three phases, namely (1) recovery of material samples from the lower head of the TMI-2 reactor, (2) examination and analysis of the lower head samples and the preparation and testing of archive mate… more
Date: June 1, 1990
Creator: Diercks, D. R. & Neimark, L. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development of creep resistant austenitic stainless steels for advanced steam cycle superheater application. [Uses of radiation effects to guide alloy development]

Description: The compositions of several 14Cr-16Ni austenitic stainless steels were modified with combinations of minor and residual alloying elements to produce excellent creep strength based on unique precipitate microstructures. These modifications produce fine MC and phosphide precipitates in the matrix for strength and various coarser carbide phases along the grain boundaries for ductility and rupture resistance. Creep-rupture resistance of these modified 14-16 steels is much better than that of type 3… more
Date: January 1, 1987
Creator: Maziasz, P. J. & Swindeman, R. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Hot corrosivity of coal gasification products on gas turbine alloys. Summary report, 15 April 1978-15 November 1979

Description: The results of this investigation have produced mechanisms for the hot corrosion of a number of pure metals and alloys in the types of atmospheres likely to be obtained in turbines using coal conversion products as fuel. The results of these mechanistic studies suggest the following conclusions regarding application of alloys in these situations: (1) Simple Cr/sub 2/O/sub 3/-forming alloys of both Co and Ni have good hot corrosion resistance to most of the deposits likely to form in turbines bu… more
Date: January 1, 1979
Creator: Meier, G.H. & Gulbransen, E.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Report covering examination of parts from downhole steam generators. [Combustor head and sleeve parts]

Description: Combustor head and sleeve parts were examined by using optical and scanning electron metallography after use in oxygen/diesel and air/diesel downhole steam generators. The degradation of the different alloy components is described in terms of reactions with oxygen, sulfur and carbon in the presence of cyclic stresses, all generated by the combustion process. Recommendations are presented for component materials (alloys and coatings) to extend component lives in the downhole steam generators. 9 … more
Date: August 1, 1983
Creator: Pettit, F. S. & Meier, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Characterization of an aged WESF capsule

Description: A joint effort by SNLA and ORNL was initiated for a detailed characterization of an 18-year-old WESF /sup 137/Cs source which has been used in the Sandia Irradiator for Dried Sewage Solids. The study included evaluation of the inner and outer stainless steel capsules by optical metallography, electron microprobe, and physical testing. Analysis of the residual atmospheres within the two containers was also done. The CsCl was analyzed for isotopic content and impurities. No potential problem area… more
Date: July 1, 1983
Creator: Kenna, B.T. & Schultz, F.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cracking and healing behavior of UO/sub 2/ as related to pellet-cladding mechanical interaction. Interim report, July 1976

Description: A direct-electrical-heating apparatus has been designed and fabricated to investigate those nuclear-fuel-related phenomena involved in the gap closure-bridging annulus formation mechanism that can be reproduced in an out-of-reactor environment. Prototypic light-water-reactor UO/sub 2/ fuel-pellet temperature profiles have been generated utilizing high flow rates (approximately 700 liters/min) of helium coolant gas, and a recirculating system has been fabricated to permit tests of up to 1000 h. … more
Date: October 1, 1976
Creator: Kennedy, C R; Yaggee, F L; Voglewede, J C; Kupperman, D S; Wrona, B J; Ellingson, W A et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cesium chloride compatibility testing program. Annual report, fiscal year 1983

Description: A program was started in FY 1982 to evaluate the compatibility of WESF-produced CsCl with 316L stainless steel under the thermal conditions that would be encountered in a geologic repository. The major part of the program involves compatibility testing of six standard WESF CsCl capsules at a maximum CsCl/metal interface temperature of 450/sup 0/C. The capsules are allowed to self heat to the test temperature in insulated containers and then held at temperature for 2200 to 32,000 h. After therma… more
Date: March 1, 1984
Creator: Bryan, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending December 31, 1981

Description: The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1982-1986 in which projects are organized according to fossil energy technologies. This report is divided into parts and chapters… more
Date: April 1, 1982
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Materials research for the clean utilization of coal. Quarterly progress report, January-March 1980

Description: An interpretive report, summarizing erosive wear failures in coal conversion pilot plants was completed, reviewed by DOE and submitted for NBS editorial review. The Failure Information Center transmitted 198 abstracts and 8 hard-copy reports to industry. Compressive yield measurement of MHD refractories at 1400/sup 0/C, 1500/sup 0/C, and 1580/sup 0/C are presented for loading at 0.0002 in/min. The electrical conductivity of YCrO/sub 3/ doped with five percent Ca has been measured in a highly re… more
Date: January 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Metals and Ceramics Division progress report for period ending September 30, 1991

Description: This report provides a brief overview of the activities and accomplishments of the Metals and Ceramics (M C) Division during fiscal year (FY) 1991. The division is organized to provide technical support, primarily in the area of high-temperature materials, for the various technologies being developed by the US Department of Energy (DOE). Activities span the range from basic research (through applied research and engineering development) to industrial interactions (through cooperative research a… more
Date: March 1, 1992
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Failure analysis of radioisotopic heat source capsules tested under multi-axial conditions

Description: In order to qualify small radioisotopic heat sources for a 25-yr design life, multi-axial mechanical tests were performed on the structural components of the heat source. The results of these tests indicated that failure predominantly occurred in the middle of the weld ramp-down zone. Examination of the failure zone by standard metallographic techniques failed to indicate the true cause of failure. A modified technique utilizing chemical etching, scanning electron microscopy, and energy dispers… more
Date: unknown
Creator: Zielinski, R. E.; Stacy, E. & Burgan, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Examination of Stainless Steel-Clad Connecticut Yankee Fuel Assembly S004 After Storage in Borated Water

Description: A Connecticut Yankee fuel assembly (S004) was tested nondestructively and destructively. It was concluded that no obvious degradation of the 304L stainless steel-clad spent fuel from assembly S004 occurred during 5 y of storage in borated water. Furthermore, no obvious degradation due to the pool environment occurred on 304 stainless steel-clad rods in assemblies H07 and G11, which were stored for shorter periods but contained operationally induced cladding defects. The seam welds in the claddi… more
Date: September 1, 1982
Creator: Langstaff, D. C.; Bailey, W. J.; Johnson, A. B., (Jr.); Landow, M. P.; Pasupathi, V. & Klingensmith, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Postirradiation examination results from SP-1

Description: This paper describes the postirradiation examination results from several of the fuel pins irradiated in the SP-1 test. The SP-1 test is the first of two tests irradiated in EBR-II to be examined. These tests are designed to provide a direct comparison of the performance potential of UO/sub 2/ and UN fuel pins under conditions anticipated for the SP-100 reactor. In addition, these tests examine various feasibility issues associated with each fuel system. These issues include: the high temperatu… more
Date: January 1, 1986
Creator: Karnesky, R.A. & Mason, R.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Orientation dependency of mechanical properties of 1950's vintage Type 304 stainless steel weldment components before and after low temperature neutron irradiation

Description: Databases of mechanical properties for both the piping and reactor vessels at the Savannah River Site (SRS) were developed from weldment components (base, weld, and weld heat-affected-zone (HAZ)) of archival piping specimens in the unirradiated and irradiated conditions. Tensile, Charpy V-notch (CVN), and Compact Tension C(T) specimens were tested at 25 and 125C before and after irradiation at low temperatures (90 to 150C) to levels of 0.065 to 2.1 dpa. irradiation hardened the weldment compone… more
Date: January 1, 1992
Creator: Sindelar, R.L. & Caskey, G. R., Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Advanced LMFBR fuel cladding susceptability to stress corrosion due to reprocessing impurities

Description: The potential degradation of LMFBR fuel cladding alloys by chlorides, when used in metallic fuel systems, was evaluated. The alloys tested were D-9 and HT-9 stainless steels, austenitic and ferritic alloys respectively. These two alloys were tested in parallel with and their performance compared to the austenitic stainless steel Type 316. All alloys were tested for 7400 hours in a stress rupture environment with chloride exposure at either 550/degree/C 650/degree/C. None of the alloys tested we… more
Date: March 1, 1987
Creator: Henslee, S. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of welding on weldment mechanical performance in two austenitic steels

Description: The effect of autogenous gas-tungsten arc-welding on the mechanical performance of two austenitic steels has been evaluated for cable jackets of force-cooled superconductor coils. The original candidate material was Nitronic 40, a nitrogen-strengthened stainless steel. The in-situ reaction heat treatment at 700/sup 0/C necessary for the formation of the superconducting A15 phase results in severe degradation of the cryogenic tensile ductility in the weld metal. The search for an alternate mater… more
Date: June 1, 1982
Creator: Strum, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen