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Transport and deposition of activation products in a helium cooled fusion power plant

Description: The transport and deposition of neutron activation products in a helium cooled tokamak fusion power plant are investigated. Stainless steel is used as coolant channel material for a helium/steam system. The important gamma emitting nuclides /sup 56/Mn, /sup 54/Mn, /sup 57/Co, /sup 58/Co, /sup 60/Co, /sup 51/Cr, and /sup 99/Mo are considered. The dominant release mechanism identified is direct daughter recoil emission from (n,x) type reactions. Corrosion and evaporation are discussed. The radion… more
Date: September 1, 1980
Creator: Bickford, W.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Theoretical and experimental studies of fixed-bed coal gasification reactors. Final report

Description: A laboratory fixed-bed gasification reactor was designed and built with the objective of collecting operational data for model validation and parameter estimation. The reactor consists of a 4 inch stainless steel tube filled with coal or char. Air and steam is fed at one end of the reactor and the dynamic progress of gasification in the coal or char bed is observed through thermocouples mounted at various radial and axial locations. Product gas compositions are also monitored as a function of t… more
Date: September 1, 1983
Creator: Joseph, B.; Bhattacharya, A.; Salam, L. & Dudukovic, M.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of nominal and crack-tip strain rate on IGSCC susceptibility in CERT tests

Description: Constant extension rate tests have been performed on sensitized Type 316 stainless steel in oxygenated water (8 ppM O/sub 2/) containing chloride ion impurities (0.5 ppM) over a range of strain rates from 10/sup -5/ to 2 x 10/sup -7/ s/sup -1/. The susceptibility to IGSCC (as quantified by parameters such as crack length at failure) increases with a decrease in strain rate. A model consistent with the observed and postulated crack growth behavior and with a fracture criterion is presented and u… more
Date: September 1, 1983
Creator: Maiya, P.S. & Shack, W.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Swedish nuclear waste efforts

Description: After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreproces… more
Date: September 1, 1981
Creator: Rydberg, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Improvement of the mechanical reliability of monolithic refractory linings for coal gasification process vessels. Final report

Description: Eighteen heat-up tests were run on nine standard and experimental dual component monolithic refractory concrete linings. These tests were run with a five foot diameter by 14-ft high Pressure Vessel/Test Furnace designed to accommodate a 12-inch thick by 5-ft high refractory lining, heat the hot face to 2000/sup 0/F and expose the lining to air or steam pressures up to 150 psig. Results obtained from standard type linings in the test facility indicated that lining degradation duplicated that obs… more
Date: September 1, 1981
Creator: Potter, R.A. (comp.)
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ORNL irradiation creep facility

Description: A machine was developed at ORNL to measure the rates of elongation observed under irradiation in stressed materials. The source of radiation is a beam of 60 MeV alpha particles from the Oak Ridge Isochronous Cyclotron (ORIC). This choice allows experiments to be performed which simulate the effects of fast neutrons. A brief review of irradiation creep and experimental constraints associated with each measurement technique is given. Factors are presented which lead to the experimental choices ma… more
Date: September 1, 1980
Creator: Reiley, T. C.; Auble, R. L.; Beckers, R. M.; Bloom, E. E.; Duncan, M. G.; Saltmarsh, M. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Small-angle neutron scattering from voids in neutron irradiated type 304 stainless steel. [E > 0. 1 MeV]

Description: Preliminary small-angle neutron scattering results designed to investigate the structure of voids in neutron-irradiated polycrystalline annealed type 304 stainless steel were obtained. Specimens were subjected to irradiation at 400/sup 0/C to a fluence of 1.6 x 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV). Void interference effects were seen for voids having an average diameter of about 290 A. The distribution was ''gas-like''with an exclusion distance of 307 A. 1 figure, 1 table. (RWR)
Date: September 1, 1977
Creator: Child, H.R. & Spooner, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Corrosion of ferrous alloys in eutectic lead-lithium environments

Description: Corrosion data have been obtained on austenitic prime candidate alloy (PCA) and Type 316 stainless steel and ferritic HT-9 and Fe-9Cr-1Mo steels in a flowing Pb-17 at. % Li environment at 727 and 700 K (454 and 427/sup 0/C). The results indicate that the dissolution rates for both austenitic and ferritic steels in Pb-17Li are an order of magnitude greater than in flowing lithium. The influence of time, temperature, and alloy composition on the corrosion behavior in Pb-17Li is similar to that in… more
Date: September 1, 1983
Creator: Chopra, O. K. & Smith, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The effect of yield strength on side-bonding upset welds

Description: During the course of 9{degree} tapered side-bonding resistance upset weld development at Mound, various studies have been conducted to evaluate the effect of yield strength on welds in 304L stainless steel. The results of these studies have concluded that at high yield strengths there may be a minor reduction in the length of Class 2 or better bond. Satisfactory welds have been produced with materials having yield strengths ranging from 36.0 to 141.0 ksi. However, when body yield strengths exce… more
Date: September 24, 1991
Creator: Miller, R. G. & Perkins, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cross Section Evaluation Working Group benchmark specifications. Volume 2. Supplement

Description: Neutron and photon flux spectra have been measured and calculated for the case of neutrons produced by D-T reactions streaming through a cylindrical iron duct surrounded by concrete. Measurements and calculations have also been obtained when the iron duct is partially filled by a laminated stainless steel and borated polyethylene shadow bar. Schematic diagrams of the experimental apparatus is included.
Date: September 1, 1986
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation creep and swelling of AISI 316 to exposures of 130 dpa at 385 to 400/sup 0/C

Description: The creep and swelling of AISI 316 stainless steel have been studied at 385 to 400/sup 0/C in EBR-II to doses of 130 dpa. Most creep capsules were operated at constant stress and temperature but mid-life changes in these variable were also made. This paper concentrates on the behavior of the 20% cold-worked condition but five other conditions were also studied. Swelling at less than or equal to00/sup 0/C was found to lose the sensitivity to stress exhibited at higher temperatures while the cree… more
Date: September 1, 1987
Creator: Garner, F. A. & Porter, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Rapid solidification processing of iron-base alloys for structural applications

Description: The response of iron-base alloys to rapid solidification is reviewed with an emphasis on the effects of processing on the microstructure and mechanical property behavior. The processing topics addressed are powder atomization, powder consolidation, joining, and thermal-mechanical exposure. The value of rapid solidification processing (RSP) lies in the ability to promote compositional homogeneity and retention of fine and stable (to high temperatures) microstructures. Achieving the maximum benef… more
Date: September 1, 1991
Creator: Flinn, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fracturing of simulated high-level waste glass in canisters

Description: Waste-glass castings generated from engineering-scale developmental processes at the Pacific Northwest Laboratory are generally found to have significant levels of cracks. The causes and extent of fracturing in full-scale canisters of waste glass as a result of cooling and accidental impact are discussed. Although the effects of cracking on waste-form performance in a repository are not well understood, cracks in waste forms can potentially increase leaching surface area. If cracks are minimize… more
Date: September 1, 1981
Creator: Peters, R. D. & Slate, S. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of rapid solidification on stainless steel weld metal microstructures and its implications on the Schaeffler diagram

Description: An investigation was carried out to determine the effect of rapid solidification on the weld metal microstructure of austenitic stainless steels and its implication on the ferrite constitution diagram. A wide variety of stainless steels were laser welded at different welding speeds and laser power levels. Results indicate that both weld pool cooling rate and the postsolidification solid state cooling rates have a profound effect on the microstructures. For the steels investigated, the microstru… more
Date: September 1, 1987
Creator: David, S. A.; Vitek, J. M.; Reed, R. W. & Hebble, T. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of nitronic 50 fusion welding techniques for 4 K service

Description: The Mirror Fusion Test Facility (MFTF-B) is a large magnetic fusion energy experiment in the tandem mirror configuration. The requirement that each pair of Yin-Yang magnets, one pair at each end of the experiment, not undergo excessive lateral motion during seismic events was found to require excessively thick (> 12.7 mm) walled tubing in the support-struts, which accelerated the flow of heat inward to the 4 K magnet case from the nearby 300 K wall of the rector vessel, when any of the Cr-Ni au… more
Date: September 23, 1981
Creator: Dalder, E.N.C. & Juhas, M.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Survey of matrix materials for solidified radioactive high-level waste

Description: Pacific Northwest Laboratory (PNL) has been investigating advanced waste forms, including matrix waste forms, that may provide a very high degree of stability under the most severe repository conditions. The purpose of this study was to recommend practical matrix materials for future development that most enhance the stability of the matrix waste forms. The functions of the matrix were reviewed. Desirable matrix material properties were discussed and listed relative to the matrix functions. Pot… more
Date: September 1, 1981
Creator: Gurwell, W.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Correlation of waterside corrosion and cladding microstructure in high-burnup fuel and gadolinia rods

Description: Waterside corrosion of the Zircaloy cladding has been examined in high-burnup fuel rods from several BWRs and PWRs, as well as in 3 wt % gadolinia burnable poison rods obtained from a BWR. The corrosion behavior of the high-burnup rods was then correlated with results from a microstructural characterization of the cladding by optical, scanning-electron, and transmission-electron microscopy (OM, SEM, and TEM). OM and SEM examination of the BWR fuel cladding showed both uniform and nodular oxide … more
Date: September 1, 1989
Creator: Chung, H.M. (Argonne National Lab., IL (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Influence of a flowing-lithium environment on the fatigue and tensile properties of Type 316 stainless steel

Description: Low-cycle fatigue and tensile data have been obtained on Type 316 stainless steel in a flowing lithium environment of controlled purity. The results show that the fatigue life of the steel in flowing lithium at 755 K is greater than in air. Preexposure of the material to lithium reduces fatigue life. The reduction in fatigue life may be attributed to the formation of a weak ferrite layer after lithium exposure. Tensile data for cold-worked Type 316 stainless steel indicate that at temperatures … more
Date: September 1, 1983
Creator: Chopra, O. K. & Smith, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reference commercial high-level waste glass and canister definition.

Description: This report presents technical data and performance characteristics of a high-level waste glass and canister intended for use in the design of a complete waste encapsulation package suitable for disposal in a geologic repository. The borosilicate glass contained in the stainless steel canister represents the probable type of high-level waste product that will be produced in a commercial nuclear-fuel reprocessing plant. Development history is summarized for high-level liquid waste compositions, … more
Date: September 1, 1981
Creator: Slate, S.C.; Ross, W.A. & Partain, W.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Long-term aging of cast stainless steels: Mechanisms and resulting properties

Description: Mechanical property data are presented from Charpy-impact, tensile, and J-R curve tests for several heats of cast stainless steel aged up to 10,000 h at 450, 400, 350, 320, and 290/sup 0/C. The results indicate that thermal aging increases the tensile strength and decreases the impactenergy, J/sub IC/ and tearing modulus of the steels. Also, the ductile-to-brittle transition curve shifts to higher temperatures. The low-carbon CF-3 steels were the most resistant and the molybdenum-containing hig… more
Date: September 1, 1987
Creator: Chopra, O. K. & Chung, H. M.
Item Type: Refine your search to only Article
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
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LLTR relief system materials evaluation. [LMFBR]

Description: The scope of Subtask Y4, Sodium/Water Reaction Recovery of Work Package Task Number SG037, Large Sodium/Water Reaction Test and Analysis, is to establish procedures for LMFBR plant cleanup and recovery following sodium/water reaction (SWR) events. Encompassed within the recovery aspects of this scope is the evaluation of steam generator and relief systems material behavior following SWR events. Of particular concern is the potential for stress corrosion cracking (SCC) that may occur in the stea… more
Date: September 1, 1979
Creator: Roit, W.J. & Ring, P.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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