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Compatibility testing of vitrified waste forms

Description: An experimental program to evaluate candidate metals for use in the fabrication of canisters for long-term storage of vitrified radioactive wastes is described. The long-term compatibility of the candidate metal both with the contained vitrified radioactive waste and with the external environments expected in possible final storage locations will be determined. These tests involve heating combinations of waste forms and canister metals in intimate contact for up to 50,000 hr to accelerate any r… more
Date: March 6, 1978
Creator: Rankin, W.N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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TCT hybrid preconceptual blanket design studies

Description: The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal d… more
Date: January 1, 1978
Creator: Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coal Technology Program. Progress report for November 1977

Description: A block of Pittsburgh seam bituminous coal and a block of Wyodak subbituminous coal were pyrolyzed under reducing gas in support of in situ gasification. Information from previously completed block pyrolysis of bituminous coal under an argon atmosphere show that differences in evolved gas result from differences in heating rates. Compared to block pyrolysis at 0.3 C/sup 0//min, block pyrolysis at 3 C/sup 0//min produces less gas but gas with a higher heating value, yielding a higher overall pyr… more
Date: January 1, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Elastic and Plastic Strains and the Stress Corrosion Cracking of Austenitic Stainless Steels. Progress Report, April 30, 1977--December 30, 1977

Description: A newly developed test environment based on NaCl, Na/sub 2/SO/sub 4/, and HCl has provided some insight to several aspects of SCC in a transformable austenitic stainless steel. Current vs. time curves indicated the presence of the formation of a ''protective'' film which drastically reduced the anodic current leading to failure. This film, not indicated by the polarization curves, is subject to highly localized damage such as pitting. Thus, although it allows only very small corrosion currents,… more
Date: January 1, 1978
Creator: Troiano, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interaction of xenon light with the surface of 304 stainless steel

Description: Laser amplifier frames fabricated from Type 304 stainless steel are known to cause damage to glass lenses by ejecting particles which are deposited on the lenses. High energy pulses of xenon light interact with the steel surface to produce damage sites. Heat treatment and surface cleaning procedures greatly affect the surface stability of the steel and influence contamination generated by the steel. It is believed that inclusions and/or carbides play a role, and the size of damage sites observe… more
Date: February 14, 1978
Creator: Krenzer, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Materials technology for accelerator production of fissile isotopes

Description: The materials used for the accelerator production of fissile isotopes must enable the facility to achieve maximum fuel production at a minimum cost. Neutron production in the target would be maximized by use of thorium cooled with Pb--56 percent Bi or with sodium. The thorium should be ion-plated with approximately 1 mil of nickel or stainless steel for retention of fission products. The target container will have to be replaced at frequent intervals because of the copious quantities of neutron… more
Date: February 1, 1978
Creator: Horak, J.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Localized corrosion and stress corrosion cracking behavior of austenitic stainless steel weldments containing retained ferrite. Annual progress report, June 1, 1977--March 31, 1978

Description: Localized corrosion (pitting) experiments have been performed on single-phase austenitic 304 stainless steels and on duplex 304 steels containing 6 to 8% retained delta ferrite as a result of rapid solidification (welding). Experimental variables included thermomechanical treatment, solution pH, chloride concentration and solution temperature.
Date: March 1, 1978
Creator: Savage, W. F. & Duquette, D. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electrode polarization studies in hot corrosion systems. Progress report, June 1, 1977--May 31, 1978

Description: Analysis of thermodynamic models pertaining to coal gasification is near completion. Model I, comprising a gas phase and a molten salt phase, pertains to laboratory materials testing; Model II incorporates as well a solid carbon phase and is intended to model typical gasifier environments. Anodic and cathodic polarization measurements on iron, 1018 steel, nickel, and 304 and 316 stainless steel have been performed in molten sodium carbonate under air and oxygen; tests under reducing environment… more
Date: February 1, 1978
Creator: Devereux, O.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of valve springs from hydrogen compressor at Solvent Refined Coal Plant, Wilsonville, Alabama

Description: Failure of hydrogen compressor valve springs at the Wilsonville, Alabama, Solvent Refined Coal Plant caused a total plant shutdown. Type 304 stainless steel springs had been substituted for two of three alloy X750 springs. Mainly because of their geometry, the type 304 stainless steel springs operated at a higher stress than the proper springs, and it is not surprising that they failed. The only as-fractured surface was on the alloy X750 spring. Edge damage caused by rubbing of the springs agai… more
Date: March 1, 1978
Creator: King, R. T.; Crouse, R. S.; Leslie, B. C.; Rose, E. T. & Houck, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Si and Ti on the phase stability and swelling behavior of AISI 316 stainless steel. [Neutron and heavy ion irradiations]

Description: Swelling behavior of neutron irradiated stainless steels is influenced by solute segregation and preciptation phenomena. The extent to which in-reactor swelling behavior may be simulated by heavy ion irradiation depends upon the extent to which in-reactor phase changes are reproduced; this question is addressed by comparing the precipitation behavior under neutron irradiation with behavior during 4 MeV Ni ion irradiation for AISI 316 stainless steel and a related stainless steel containing addi… more
Date: January 1, 1978
Creator: Lee, E.H.; Rowcliffe, A.F. & Kenik, E.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Damage of metal surfaces by a hot, dense deuterium plasma

Description: The effect of differences in alloy chemistry and systematic changes in microstructural interface density on the occurrence of unipolar arcing was studied. The effect of thermionic emission is examined by comparing the refractory metals W, Nb, and Nb-751 alloy to the non-refractory stainless steels, AISI 304, 316 and Nimonic PE-16. The effect of alloying additions is examined by comparing Mo containing 316 and Mo free 304 stainless steels as well as Zr containing Nb-751 and Zr free Nb. The effec… more
Date: January 1, 1978
Creator: Panayotou, N.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Materials technology for coal-conversion processes. Sixteenth quarterly report, October--December 1978

Description: Refractories for slag containment, nondestructive evaluation methods, corrosion, erosion, and component failures were studied. Analysis of coal slags reveal ferritic contents of 18 to 61%, suggesting a partial pressure of 0/sub 2/ in the slagging zone of approx. 10/sup -2/ to 10/sup -4/ Pa. A second field test of the high-temperature ultrasonic erosion-monitoring system was completed. Ultrasonic inspecton of the HYGAS cyclone separator shows a reduced erosive-wear rate at 5000 h in the stellite… more
Date: January 1, 1978
Creator: Ellingson, W A
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control of beryllium-7 in liquid lithium

Description: Radiation fields created by the production of /sup 7/Be in lithium of the Fusion Materials Irradiation Test (FMIT) Facility can be sufficiently high to prevent contact maintenance of system components. Preliminary experiments have shown that /sup 7/Be will adhere strongly to the FMIT piping and components and a good control method for /sup 7/Be must be developed. The initial experiments have been conducted in static stainless steel capsules and a Modified Thermal Convection Loop (MTCL). The ave… more
Date: December 1, 1978
Creator: Anantatmula, R. P.; Brehm, W. F.; Baldwin, D. L. & Bevan, J. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Inertia and friction welding of type 1100 aluminum to type 316 stainless steel

Description: The inertia and friction-welding processes were evaluated for joining Type 1100-H14 aluminum to Type 316 VIM VAR stainless steel. While both processes consistently produce joints whose strength exceed the aluminum base metal, 100 percent bonding has not been reliably achieved. This deficiency points out the need for the development of nondestructive testing techniques for this type of joint. Additionally, solid state volume diffusion did not appear to be a satisfactory explanation for the inert… more
Date: December 1, 1978
Creator: Perkins, M.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High-temperature piping-design technology, January-March 1978. [LMFBR]

Description: The overall objectives of the High-Temperature Piping Design Technology Program are: to provide design methodology for elevated temperature piping systems, based on experiences with FFTF, LMEC, and CRBRP designs and on operating high-temperature piping systems; to assess the validity of using current high-temperature Code Case 1592 design rules on piping systems; to investigate critical piping system design problems from the design criteria viewpoint; and to increase the confidence level in hig… more
Date: January 1, 1978
Creator: Naugle, F. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High-temperature piping design technology. 26-high-temperature piping design, July-September 1978

Description: Objectives were to provide design methodology for elevated-temperature piping systems, to assess the validity of current high-temperature Code Case 1592 design rules for piping systems, to investigate critical piping system design problems, and to demonstrate the conservatism of the high-temperature design rules for piping. This document reports on a number of major tasks in support of the above objectives. (DLC)
Date: January 1, 1978
Creator: Jetter, R. I.; Naugle, F. V. & Jaquay, K. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal and hydraulic analysis of a cylindrical blanket module design for a tokamak reactor

Description: Various existing blanket design concepts for a tokamak fusion reactor were evaluated and assessed. These included the demonstration power reactors of ORNL, GA and others. As a result of this study, a cylindrical, modularized blanket design concept was developed. The module is a double-walled, stainless steel 316 cylinder containing liquid lithium for tritium breeding and is cooled by pressurized helium. Steady state and transient thermal conditions under normal and some off-design conditions we… more
Date: October 1, 1978
Creator: Lee, A. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of various NDT techniques to determine their feasibility for detecting thin layers of ferrite on Type 316 stainless steel

Description: The applicability of various NDT techniques for detecting thin layers of ferrite on Type 316 stainless steel cladding was studied. The ability to detect sodium-induced ferrite layers on fuel pins would allow an experimental determination of the fuel pin temperature distribution. The research effort was broken down into three basic sections. Phase one consisted of a theoretical determination of the ferrite detection potential of each of the propsed NDT techniques. The second phase consisted of p… more
Date: September 1, 1978
Creator: Dudder, G. B.; Atteridge, D. G. & Davis, T. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel adjacency effects on fast reactor cladding mechanical properties. [LMFBR]

Description: Simulated transient tests were conducted on 234 cladding specimens from EBR-II irradiated mixed oxide fuel pins; approximately 75% of the specimens were from the fuel column region, with the remainder from the plenum and below the fuel column. The cladding specimens were taken from the N-E, N-F,, PNL-9, PNL-10, PNL-11, P-23A, P-23B, P-23C, and WSA-3 fuel pins irradiated at 15.2 to 37 KW/cm to burnup levels from 11 to 110 MWd/Kg. All the fuel pins used 20% cold worked Type 316 stainless steel cl… more
Date: December 6, 1978
Creator: Hunter, C. W. & Johnson, G. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Creep-fatigue interactions in an austenitic stainless steel

Description: A phenomenological model of the interaction between creep and fatigue in Type 304 stainless steel at elevated temperatures is presented. The model is based on a crack-growth equation and an equation governing cavity growth, expressed in terms of current plastic strain and plastic strain rate. Failure is assumed to occur when a proposed interaction equation is satisfied. Various parameters of the equations can be obtained by correlation with continuously cycling fatigue and monotonic creep-ruptu… more
Date: January 1, 1978
Creator: Majumdar, S. & Maiya, P.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Use of generalized regression models for the analysis of stress-rupture data

Description: The design of components for operation in an elevated-temperature environment often requires a detailed consideration of the creep and creep-rupture properties of the construction materials involved. Techniques for the analysis and extrapolation of creep data have been widely discussed. The paper presents a generalized regression approach to the analysis of such data. This approach has been applied to multiple heat data sets for types 304 and 316 austenitic stainless steel, ferritic 2/sup 1///s… more
Date: January 1, 1978
Creator: Booker, M. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Effects of radiations from transuranium nuclides on container surfaces. [/sup 242/Cm and /sup 252/Cf]

Description: Container materials for short-lived transuranium nuclides such as /sup 242/Cm and /sup 252/Cf may be implanted with sufficiently high concentrations of helium to cause surface blistering and other deleterious effects in some environments. Platinum and stainless steel surfaces adjacent to solid /sup 242/Cm-oxide deposits showed no blisters after room-temperature exposures, but formed porous, distorted layers on postexposure heating. Platinum surfaces adjacent to solid /sup 252/Cf-oxide deposits,… more
Date: January 1, 1978
Creator: McDonell, W.R. & Dillich, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness

Description: A blanket/shield assembly for a fusion reactor has been designed through extensive optimization studies. The design was optimized under the following constraints: (a) minimum overall thickness, (b) tritium breeding ratio of 1.10, (c) thermal energy recovery of 90%, (d) acceptably flat temperature distribution, and (e) excluding all ''exotic'' or problematic materials. The optimized blanket/shield has an overall thickness of 36 cm and conforms with all the above requirements. All tritium breedin… more
Date: January 1, 1978
Creator: Gerstl, S.A.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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