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Leaching studies of low-level radioactive waste forms

Description: A research program has been under way at the Brookhaven National Laboratory to investigate the radionuclide release behavior of ion exchange bead resin waste solidified in Portland cement. An important aspect of this program is to develop and evaluate testing procedures and methodologies which enable the long-term performance evaluation of waste forms under simulated field conditions. Cesium and strontium release behavior using a range of testing procedures, including intermittent leachant flow… more
Date: January 1, 1985
Creator: Dayal, R.; Arora, H.; Clinton, J.C. & Milian, L.
Partner: UNT Libraries Government Documents Department
open access

Sodium compatibility of HT-9 and Fe-9Cr-1Mo steels

Description: Ferritic steels have been receiving significant attention for possible use as steam generator tubing, and as alternate structural materials for liquid-metal heat-transport systems in commercial fast reactors, fusion reactors, etc. The materials are chosen on the basis of their high thermal conductivity, resistance to stress-corrosion-cracking in aqueous and steam environments, favorable fabricability and fairly low cost. These steels are available in several classes based on the microstructure … more
Date: November 1, 1985
Creator: Anantatmula, R. P. & Brehm, W. F.
Partner: UNT Libraries Government Documents Department
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Advanced materials for geothermal energy processes

Description: The primary goal of the geothermal materials program is to ensure that the private sector development of geothermal energy resources is not constrained by the availability of technologically and economically viable materials of construction. This requires the performance of long-term high risk GHTD-sponsored materials R and D. Ongoing programs described include high temperature elastomers for dynamic sealing applications, advanced materials for lost circulation control, waste utilization and di… more
Date: August 1, 1985
Creator: Kukacka, L. E.
Partner: UNT Libraries Government Documents Department
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Controlled powder morphology experiments in megabar 304 stainless steel compaction

Description: Experiments with controlled morphology including shape, size, and size distribution were made on 304L stainless steel powders. These experiments involved not only the powder variables but pressure variables of 0.08 to 1.0 Mbar. Also included are measured container strain on the material ranging from 1.5% to 26%. Using a new strain controllable design it was possible to seperate and control, independently, strain and pressure. Results indicate that powder morphology, size distribution, packing d… more
Date: January 1, 1985
Creator: Staudhammer, K.P. & Johnson, K.A.
Partner: UNT Libraries Government Documents Department
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High strain rate deformation in FCC metals and alloys

Description: The effect of strain rate, and particularly of high strain rates, on deformation mechanisms in materials is of fundamental interest to those who model and analyze dynamic loading. In many materials the strain rate sensitivity is known to increase dramatically when the strain rate is raised above approx.10/sup 3/ s/sup -1/. This increase has been interpreted previously as a transmission in deformation mechanism from thermal activation control at low strain rate to dislocation drag control at hig… more
Date: January 1, 1985
Creator: Follansbee, P.S.
Partner: UNT Libraries Government Documents Department
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Survey of physical property data for several alloys. [Nitronic 33; copper C10400; copper C17510]

Description: This report summarizes an examination of physical property data available in the literature for six alloys of potential interest to the Toroidal Fusion Core Experiment in the Fusion Energy Program. The properties of thermal expansion, density, specific heat, electrical resistivity, and thermal conductivity were compiled for six alloys: Nitronic 33, a low-nickel, high manganese stainless steel; nickel-base Inconnel Alloys 625, 718, and X-750; and copper alloys C10400 and C17510. The temperatures… more
Date: August 1, 1985
Creator: Pawel, R. E. & Williams, R. K.
Partner: UNT Libraries Government Documents Department
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Application of ultrasonic waves to assess grain structure in cast stainless steel

Description: Although the ASME code requires the inspection of cast stainless steel (CSS) piping in nuclear reactors, it has not been possible to demonstrate unambiguously that current inspection techniques are adequate. Ultrasonic inspection is difficult because the microstructure of CSS can vary considerably, from elastically isotropic with equiaxed, relatively small grains to elastically anisotropic with a columnar grain structure to a combination of the two. For the near term, improvements that may incr… more
Date: April 1, 1985
Creator: Kupperman, D.S.; Reimann, K.J. & Abrego-Lopez, J.
Partner: UNT Libraries Government Documents Department
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Plant monitoring techniques and second generation designs

Description: Chemical and instrumental monitoring techniques suitable for geothermal use are described in a manner to relate them to plant operational problems and downtime avoidance. The use of these techniques permits the detection of scaling, the onset of scaling, corrosion loss, current corrosion rates and incipient heat exchanger failure. Conceptual advances are noted which simplify the research techniques to approaches that should be usable even in some low-capital well-head type power plants. 10 refs… more
Date: March 1, 1985
Creator: Kindle, C.H.; Shannon, D.W.; Robertus, R.J.; Pierce, D.D. & Sullivan, R.G.
Partner: UNT Libraries Government Documents Department
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Austenitic stainless steels for cryogenic service

Description: Presently available information on austenitic Fe-Cr-Ni stainless steel plate, welds, and castings for service below 77 K are reviewed with the intent (1) of developing systematic relationships between mechanical properties, composition, microstructure, and processing, and (2) of assessing the adequacy of these data bases in the design, fabrication, and operation of engineering systems at 4 K.
Date: September 19, 1985
Creator: Dalder, E.N.C. & Juhas, M.C.
Partner: UNT Libraries Government Documents Department
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High strain rate approx. 10/sup 6//s response of 304 stainless steel at various strains

Description: The effect of high strain rate at controlled strain levels has been investigated on 304 stainless steel. This study implements a radial shock loading design with a reliable specimen recovery. Strains were measured by plating circle grids on a split anvil design and measured after shock loading. The strain levels were controlled by varying the momentum trap geometries. The shock wave profile impinging and traveling through the specimen as obtained by hydrocode calculations is in fact a shear wav… more
Date: January 1, 1985
Creator: Johnson, K.A. & Staudhammer, K.P.
Partner: UNT Libraries Government Documents Department
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Surface stress modification for repair of stress-relieved carbon steel fabrications

Description: Pitting corrosion was observed in welded carbon steel tanks which had been stress relieved to improve resistance to stress corrosion cracking. Successful repair required the development of a cleaning and repair method which would not increase residual tensile stresses at the steel surface. An experimental study indicated that uniform residual tensile stresses of 27.6 to 34.5 megapascals (4000 to 5000 psi) remained in the plate after the original stress relief. Grinding, shot peening, and grit b… more
Date: January 1, 1985
Creator: Jenkins, C F
Partner: UNT Libraries Government Documents Department
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Prediction of environmental and strain-rate effects on the stress corrosion cracking of austenitic stainless steels

Description: The stress corrosion cracking (SCC) susceptibility of austenitic stainless steels in high-temperature water is controlled by environmental variables (e.g., dissolved oxygen, corrosion potential, impurities), microstructure (e.g., degree of sensitization), and strain rate. A phenomenological model based on the slip-dissolution mechanism and elastic-plastic fracture mechanics is presented to quantitatively describe the effects of both environment-related parameters and strain rate on SCC in const… more
Date: January 1, 1985
Creator: Maiya, P.S.
Partner: UNT Libraries Government Documents Department
open access

Leaching studies of low-level radioactive waste forms

Description: A research program has been underway at the Brookhaven National Laboratory to investigate the release of radionuclides from low-level waste forms under laboratory conditions. This paper describes the leaching behavior of Cs-137 from two major low-level waste streams, that is, ion exchange bead resin and boric acid concentrate, solidified in Portland cement. The resultant leach data are employed to evaluate and predict the release behavior of Cs-137 from low-level waste forms under field burial … more
Date: January 1, 1985
Creator: Dayal, R.; Arora, H.; Milian, L. & Clinton, J.
Partner: UNT Libraries Government Documents Department
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Cladding corrosion and hydriding in irradiated defected zircaloy fuel rods

Description: Twenty-one LWBR irradiation test rods containing ThO/sub 2/-UO/sub 2/ fuel and Zircaloy cladding with holes or cracks operated successfully. Zircaloy cladding corrosion on the inside and outside diameter surfaces and hydrogen pickup in the cladding were measured. The observed outer surface Zircaloy cladding corrosion oxide thicknesses of the test rods were similar to thicknesses measured for nondefected irradiation test rods. An analysis model, which was developed to calculate outer surface oxi… more
Date: August 1985
Creator: Clayton, J. C.
Partner: UNT Libraries Government Documents Department
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Effects of waste content of glass waste forms on Savannah River high-level waste disposal costs

Description: Effects of the waste content of glass waste forms of Savannah River high-level waste disposal costs are evaluated by their impact on the number of waste canisters produced. Changes in waste content affect onsite Defense Waste Processing Facility (DWPF) costs as well as offsite shipping and repository emplacement charges. A nominal 1% increase over the 28 wt % waste loading of DWPF glass would reduce disposal costs by about $50 million for Savannah River wastes generated to the year 2000. Waste … more
Date: January 1, 1985
Creator: McDonell, W. R. & Jantzen, Carol M.
Partner: UNT Libraries Government Documents Department
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Thermal aging of primary coolant pipe steel

Description: The long term mechanical integrity of the pipes used to carry the primary cooling water in a pressurized water nuclear reactor is of the utmost importance for safe operation. A combined atom probe field-ion microscopy (APFIM) and transmission electron microscopy (TEM) study was performed to characterize the microstructure of this cast stainless steel and to determine the changes that occur during long-term low-temperature thermal aging. The material used in this investigation was a commercial C… more
Date: January 1, 1985
Creator: Miller, M. K.; Bentley, J.; Brenner, S. S. & Spitznagel, J. A.
Partner: UNT Libraries Government Documents Department
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Investigation of cracking on a main steam isolation valve shaft from the Farley Unit No. 1 nuclear power plant

Description: Chemical analysis of the Farley Unit No. 1 MSIV shaft (No. 69C) showed that the chemical composition of the material was consistent with that expected of a Type 410 stainless steel. The microstructure observed in the base metal (tempered martensite) is consistent with that expected in a Type 410 stainless steel in the quenched and tempered condition. The hardness measurements (both R/sub c/ and Knoop) show that the hardness observed (R/sub c/ 41.3 with a KN max of 459) is significantly higher t… more
Date: January 1, 1985
Creator: Czajkowski, C.J.
Partner: UNT Libraries Government Documents Department
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Experimental Study on Impact/Fretting Wear in Heat Exchanger Tubes

Description: A data bank of field experiences with heat exchanger tube vibration reveals numerous cases of tube failures at, or near, the baffle. The objective of this study is to provide qualitative impact/fretting wear information for heat exchanger tubes through the performance of a series of tests involving the pertinent parameters: impact force level, between the tube and its support; tube to support plate hole clearance; tube support plate thickness; and tube vibration frequency. The characteristics o… more
Date: April 1985
Creator: Cha, J. H.; Wambsganss, M. W. & Jendrzejczyk, J. A.
Partner: UNT Libraries Government Documents Department
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Evaluation of the transgranular cracking phenomenon on the Indian Point No. 3 steam generator vessels

Description: A metallurgical investigation was performed on specimens from the shell of steam generators Nos. 31 and 32 of the Indian Point-3 Power Plant. The shell material exhibited high values in hardness which was indicative that relatively high residual stresses may have been present. All observed cracks were transgranular in appearance and were associated with pits on the vessels' inside surfaces. Both stress relieved and non-stress relieved specimens of SA302 Grade B material were tested in a constan… more
Date: January 1, 1985
Creator: Czajkowski, C.J.
Partner: UNT Libraries Government Documents Department
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Failure criteria used in a probabilistic fracture mechanics code

Description: Two criteria are implemented in a piping reliability analysis code to assess the stability of crack growth in pipes. One is the critical net section stress criterion. It is simple and convenient but its application is limited to very ductile materials. The other is the tearing modulus stability criterion. This criterion has a solid technical base. However, calculating the J-integral, J, and the associated tearing modulus, T, usually requires a complicated finite element method (FEM). In this pi… more
Date: January 1, 1985
Creator: Lo, T.Y.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
open access

Analysis of the effects of corrosion potential and impurities on the stress corrosion cracking of Type 304 stainless steel

Description: Intergranular stress corrosion cracking (IGSCC) of sensitized Type 304 stainless steel (SS) has been a recurrent problem in the high-temperature water environment of boiling-water-reactors (BWRs) over the past two decades. The synergistic effects of environmental and material variables on stress corrosion cracking (SCC) of Type 304 SS were investigated at 289/sup 0/C by means of constant-extension-rate-tensile (CERT) tests at a strain rate of 1 x 10/sup -6//s. Correlations among environmental v… more
Date: June 1, 1985
Creator: Maiya, P.S.; Kassner, T.F. & Ruther, W.E.
Partner: UNT Libraries Government Documents Department
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Experimental studies of actinides in molten salts

Description: This review stresses techniques used in studies of molten salts containing multigram amounts of actinides exhibiting intense alpha activity but little or no penetrating gamma radiation. The preponderance of studies have used halides because oxygen-containing actinide compounds (other than oxides) are generally unstable at high temperatures. Topics discussed here include special enclosures, materials problems, preparation and purification of actinide elements and compounds, and measurements of v… more
Date: June 1, 1985
Creator: Reavis, J.G.
Partner: UNT Libraries Government Documents Department
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Role of hydrogen embrittlement in intergranular stress corrosion cracking of sensitized Type 304 stainless steel

Description: Fixed-load Mode I/Mode III comparative tests have been conducted on lightly sensitized (EPR = 2 C/cm/sup 2/) Type 304 SS specimens in 289/sup 0/C oxygenated water with other impurity additives. Substantial susceptibility to IGSCC was shown in Mode I but no conclusive evidence for SCC was found in Mode III. These results are consistent with a hydrogen embrittlement mechanism of crack advance, but electrochemical measurements seem to accord better with a slip-dissolution mechanism. Further studie… more
Date: June 1, 1985
Creator: Ruther, W.E.; Kassner, T.F. & Nichols, F.A.
Partner: UNT Libraries Government Documents Department
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