Search Results

Advanced search parameters have been applied.
open access

EFFECT OF NEUTRON IRRADIATION ON MATERIALS SUBJECTED TO MULTI-AXIAL STRESS DISTRIBUTIONS. Quarterly Report for the Period Ending June 30, 1962

Description: Activities in a program to determine the effects of neutron irradiation on A-302B steel are reported. Plans are discussed concerning performance tests on tensile, notched tensile, tube, and Charpy specimens. An irradiation capsule design was finalized. A theoretical analysis of the critical conditions arising in a tube subjected to both internal pressure and axial load is included. (J.R.D.)
Date: August 13, 1962
Creator: Trozera, T A
Partner: UNT Libraries Government Documents Department
open access

Dimensional Behavior of the Experimental Gas-Cooled Reactor Fuel Element at Elevated Temperatures

Description: The Experimental Gas-Cooled Reactor (EGCR) fuel assemblies consist of a cluster of seven fuel elements contained in a graphite sleeve. Each element is composed of hollow cylindrical UO/sub 2/ pellets encapsulated in a type 304 stainless steel tube. The dimensional behavior of the fuel element was determined in an apparatus which simulated the thermal conditions predicted for the EGCR. Particular emphasis was placed on determining the relationship between the fuel temperature and axial expansion… more
Date: August 1, 1961
Creator: Martin, W. R. & Weir, J. R.
Partner: UNT Libraries Government Documents Department
open access

An assessment of the effects of radiation on permanent magnet material in the ALS (Advanced Light Source) insertion devices

Description: Electrons that are lost from the beam during normal operation of a synchrotron radiation source and during a beam dump at the end of a run produce both ionizing radiation and neutrons. This radiation has the potential for damaging sensitive materials, in particular those that need to be very close to the beam. The wigglers and undulators for the Advanced Light Source (ALS) at LBL will use magnetic materials such as the very high performance neodymium-iron-boron, which will be as close as 1 cm a… more
Date: August 1, 1989
Creator: Hassenzahl, W. V.; Jenkins, T. M.; Namito, Y.; Nelson, W. R. & Swanson, W. P.
Partner: UNT Libraries Government Documents Department
open access

High-Temperature Reactions of Type 304 Stainless Steel in Low Concentrations of Carbon Dioxide and Carbon Monoxide

Description: Compatibility studies of type 304 stainless steel in helium containing low concentrations of CO and CO/sub 2/ were conducted. The oxidation rates were insensitive to impurity concentrations between 0.0006--0.3 vol% in the temperature range 400--1000 deg C when P/sub co2/P/sub co/ was less than 0.66. Ratios above this value resulted initially in a slow oxidation rate, but was followed by an accelerated attack. The incubation period for the break-away varied with the P/sub co2//P/sub co/ ratio an… more
Date: August 29, 1962
Creator: Inouye, H.
Partner: UNT Libraries Government Documents Department
open access

AN EVALUATION OF MATERIALS OF CONSTRUCTION FOR THE SULFLEX AND ZIRFLEX PROCESSES

Description: concentration is not greater than four molar and the nitric acid greater than five molar. In addition, core dissolutions should be done below the boiling point, and heat transfer surface termperatures during core dissolution should be maintained below 240 deg F. Carpenter 20 is probably less satisfactory for Sulfex service because of selective weld attack. Neither Ni-o-nel, 309 SCb, or 304L is a satisfactory construction material for uninhibited Zirflex solutions. Cupric ion lowers the corrosio… more
Date: August 1, 1962
Creator: Katz, H. & Isler, R.
Partner: UNT Libraries Government Documents Department
open access

Ocean Thermal Energy Conservation (OTEC) power system development (PDS) II. Preliminary design report

Description: This report documents the results and conclusions of the PDS II, Phase I, preliminary design of a 10 MWe OTEC power system, using enhanced plate type heat exchangers, and of representative 0.2 MWe test articles. It further provides the documentation (specifications, drawings, trade studies, etc.) resulting from the design activities. The data and discussions of the technical concepts are organized to respond to the PDS II, Phase II proposal evaluation criteria. This volume, which specifically a… more
Date: August 10, 1979
Partner: UNT Libraries Government Documents Department
open access

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
open access

Reference fuel studies. Seventh quarterly report May-July 1976. [LMFBR]

Description: Task 3 of Contract AT03-76SF78003 consists of the following programs: fuel rod chemistry and thermodynamics; fuel rod engineering; fuel irradiations testing and analysis; reference structural materials. The four parts are closely interrelated and in combination are aimed at providing a sound basis for the design and performance evaluation of LMFBR mixed oxide fuel rods.
Date: August 1, 1976
Partner: UNT Libraries Government Documents Department
open access

Ocean thermal energy conversion (OTEC) power system development (PSD) II. Preliminary design report. Appendix II: supporting data

Description: The trade studies, calculations, and reports which provide the rationale for design conclusions for the 10 MWe OTEC power system are presented in this volume. These appendices include: (1) system design and optimization model; (2) system off-design performance computer model; (3) seawater system dynamics; (4) system mechanical design studies; (5) electrical design studies; (6) structural design studies; (7) tube cleaner design report and proposed brush test program; (8) heat exchangers: mechani… more
Date: August 10, 1979
Partner: UNT Libraries Government Documents Department
open access

High-velocity impact tests involving thin spherical shells of tantalum and 304 stainless steel

Description: This experimental program generated data to improve computer-code modeling of impact phenomena. The improved computation technique will be used to design a fissile-material container able to withstand a 335 m/s impact. The program involved flyer-plate-impact tests using thin shells of annealed 304 stainless steel and annealed tantalum at impact velocities of 28 to 180 m/s. No active instrumentation was used in this study; instead, all data were derived from measurements of test specimens. Pre- … more
Date: August 26, 1977
Creator: Steffan, K. L.
Partner: UNT Libraries Government Documents Department
open access

Grain boundary cavity growth under applied stress and internal pressure

Description: The growth of grain boundary cavities under applied stress and internal gas pressure was investigated. Methane gas filled cavities were produced by the C + 4H reversible CH4 reaction in the grain boundaries of type 270 nickel by hydrogen charging in an autoclave at 500/sup 0/C with a hydrogen pressure of either 3.4 or 14.5 MPa. Intergranular fracture of nickel was achieved at a charging temperature of 300/sup 0/C and 10.3 MPa hydrogen pressure. Cavities on the grain boundaries were observed in … more
Date: August 1, 1977
Creator: Mancuso, J.F.
Partner: UNT Libraries Government Documents Department
open access

In-reactor fatigue crack propagation

Description: An in-reactor fatigue experiment is being designed to determine the effect of dynamic irradiation on the fatigue crack propagation (FCP) behavior of candidate fusion first wall materials. This investigation has been prompted by studies which show gross differences in crack growth characteristics of creep rupture specimens testing by postirradiation versus dynamic in-reactor methods. The experiment utilizes miniature center-cracked-tension specimens developed specifically for in-reactor studies.… more
Date: August 1, 1979
Creator: Ermi, A. M.; Mervyn, D. A. & Straalsund, J. L.
Partner: UNT Libraries Government Documents Department
open access

Development of ultrasonic examination methods for austenitic stainless steel weld inspection

Description: Signal acquisition and analysis techniques were developed to permit locating notches placed in an austenitic stainless steel pipe weld. Ultrasonic techniques presented here utilized refracted longitudinal and shear inspection beams with a dual element, pitch-catch transducer. Sources of grain noise and the metallurgical iplications of inspecting austenitic stainless steel welds are reviewed. Data were analyzed in both time and frequency domains, and a simple frequency moment algorithm was devel… more
Date: August 1, 1977
Creator: Mech, S.J.; Michaels, T.E.; Emmons, J.S. & Sugiyama, M.M.
Partner: UNT Libraries Government Documents Department
open access

Damage analysis and fundamental studies. Quarterly progress report, April-June 1980

Description: The DAFS program element is a national effort composed of contributions from a number of National Laboratories and other government laboratories, universities, and industrial laboratories. It was organized by the Materials and Radiation Effects Branch, Office of Fusion Energy, DOE, and a Task Group on Damage Analysis and Fundamental Studies which operates under the auspices of that Branch. The purpose of this series of reports is to provide a working technical record of that effort for the use … more
Date: August 1, 1980
Partner: UNT Libraries Government Documents Department
open access

Condensation of fuel onto the above-core structure during an LMFBR core-disruptive accident

Description: Condensation of a pure, saturated vapor onto a vertical, melting substrate is analyzed for both one- and two-material situations. Examination of the one-material situation indicates that the solution to the full transient condensation-induced melting problem may be approximated by using a transient, conduction-only model for short times and a steady-state, flowing-film model for long times. This concept is extrapolated to the two-material situation in order to obtain a simulation of the transie… more
Date: August 1, 1977
Creator: Erdman, C.A. Reynolds, A.B.
Partner: UNT Libraries Government Documents Department
open access

Creep of 304 LN and 316 L stainless steels at cryogenic temperatures

Description: Creep behavior of Type 304 LN plate and 316 L shielded-metal-arc (SMA)-deposited stainless weld metal was investigated at 4/sup 0/K. Testing was performed at constant load in a creep machine with a cryostat designed for long-term stability. Both transient and steady-state creep were observed during tests lasting over 2000 hours. Steady-state creep rates were much greater than expected from extrapolations of 300-K creep data. Creep rates on the order of 10/sup -10/ s/sup -1/ were observed at str… more
Date: August 7, 1985
Creator: Roth, L. D.; Manhardt, A. E.; Dalder, E. N. C. & Kershaw, R. P., Jr.
Partner: UNT Libraries Government Documents Department
open access

First wall costs of an ion-beam fusion reactor

Description: This paper parametrically investigates the effects of microexplosion energy on the first wall costs of a 4000 MW/sub t/ ion-beam initiated, inertially confined fusion reactor for several first wall materials. The thermodynamic models and the results for microexplosion energies between 400 and 4000 MJ are presented. A solid stainless steel or a composite isotropic graphite over stainless steel first wall can operate for a year at a cost of 0.6 mills per kWh gross electric power output.
Date: August 1, 1977
Creator: Hovingh, J.
Partner: UNT Libraries Government Documents Department
open access

Effects of composition on the in-reactor creep of AISI 316

Description: In-reactor tests designed to provide information on the relationship between compositional variations and irradiation-induced swelling and creep have achieved an exposure of 4.6 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) at 450/sup 0/C. Postirradiation diametral measurements of pressurized tube specimens have indicated that irradiation-induced creep of 316 stainless steel can be modified by compositional variations of minor alloying elements. There is a general trend for specimens with higher swell… more
Date: August 1, 1979
Creator: Bates, J.F. & Gilbert, E.R.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of the mechanical properties of an irradiated Type 347 stainless steel in-pile tube with a peak fluence of 4 x 10/sup 22/ n/cm/sup 2/ (>1 MeV)

Description: Results of postirradiation mechanical testing of Type 347 stainless steel specimens machined from an Engineering Test Reactor in-pile pressure tube are presented. Tests included tensile and fracture toughness at room temperature, 600/sup 0/F, 800/sup 0/F, and 1000/sup 0/F, room temperature fatigue, and delayed failure stress rupture with stresses approaching the yield stress. Immersion density measurements were also made. Specimen fluences varied up to 4 x 10/sup 22/ n/cm/sup 2/ (>1 MeV). Altho… more
Date: August 1979
Creator: Krupowicz, J. J.
Partner: UNT Libraries Government Documents Department
open access

An overview of environmental degradation of materials in nuclear power plant piping systems

Description: Piping in light water reactor (LWR) power systems is affected by several types of environmental degradation: intergranular stress corrosion cracking (IGSCC) of austenitic stainless steel piping in boiling water reactors (BWRs) has required research, inspection, and mitigation programs that will ultimately cost several billion dollars; erosion-corrosion of carbon steel piping has been observed frequently in the secondary systems of both BWRs and pressurized water reactors (PWRs); the effect of t… more
Date: August 1, 1987
Creator: Shack, W.J.
Partner: UNT Libraries Government Documents Department
open access

Environmentally assisted cracking in light water reactors

Description: Cracking in sensitized austenitic stainless steel (SS) piping and associated components in boiling water reactors (BWRs) has been observed since the mid-1960s. Proposed remedies include procedures that produce a favorable residual stress state in the weld regions, replacement of the piping with materials that are more resistant to SCC, and modification of the reactor coolant environment. During this year, studies that have important implications for all three classes of proposed remedies have b… more
Date: August 1, 1987
Creator: Shack, W. J.; Kassner, T. F.; Maiya, P. S.; Park, J. Y.; Ruther, W. E.; Kuczay, T. M. et al.
Partner: UNT Libraries Government Documents Department
open access

Description of Defense Waste Processing Facility reference waste form and canister. Revision 1

Description: The Defense Waste Processing Facility (DWPF) will be located at the Savannah River Plant in Aiken, SC, and is scheduled for construction authorization during FY-1984. The reference waste form is borosilicate glass containing approx. 28 wt % sludge oxides, with the balance glass frit. Borosilicate glass was chosen because of its high resistance to leaching by water, its relatively high solubility for nuclides found in the sludge, and its reasonably low melting temperature. The glass frit contain… more
Date: August 1, 1983
Creator: Baxter, R.G.
Partner: UNT Libraries Government Documents Department
open access

Hydrogen Sulphide Stress Corrosion Cracking in Materials for Geothermal Power. Final Report, Phase I

Description: Two point bent beam, NACE tensile, C-Ring and DCB stress intensity type specimens were employed to examine a series of steels' SSC resistance in the standard NACE solution and in several modifications pertinent to geothermal environments. Where direct comparisons were possible, the different types of tests qualitatively ranked the alloys in the same order. Of the commercially available steels examined suitable for downhole service, a fine-grained version of 4130 with additional Mo and some Cb a… more
Date: August 1, 1979
Creator: Troiano, A. R.; Hehemann, R. F. & Peterson, J. A.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen