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in creator/contributor: "Kielpinski, A.L."  
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Flow regime mapping of vertical two-phase downflow in a ribbed annulus

Description: Two-phase flow regimes have been mapped for vertical, cocurrent downflow in a narrow annulus which is partially segmented by the presence of longitudinal ribs. This geometry and flow condition has application to the analysis of a Large-Break Loss of Coolant Accident (LB-LOCA) in the production K-Reactor at the Savannah River Site (SRS). The ribbed annular geometry, particularly the presence of non-sealing ribs, gives rise to some unique phenomenological features. The flow behavior is influenced… more
Date: December 1, 1992
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Applications of Atomistic Simulation to Radioactive and Hazardous Waste Glass Formulation Development

Description: Glass formulation development depends on an understanding of the effects of glass composition on its processibility and product quality. Such compositional effects on properties in turn depend on the microscopic structure of the glass. Historically, compositional effects on macroscopic properties have been explored empirically, e.g., by measuring viscosity at various glass compositions. The relationship of composition to structure has been studied by microstructural experimental methods. More r… more
Date: March 1, 1995
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development of a thermal transient calculational tool for High Level Waste tanks

Description: Thermal design constraints exist on the processing operations in the High Level Waste (HLW) tanks of the Savannah River Site (SRS). A FORTRAN computer code was developed to provide a simple, fast, and reasonably accurate analysis tool for plant operation design. The code computes a lumped transient temperature for the liquid contents of a waste tank by modeling the liquid (slurry), the vapor space above it, the tank wall, and the cooling air outside of the tank. Results for a typical processing… more
Date: June 1, 1994
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

ITP.FOR: A code to calculate thermal transients in High Level Waste Tanks

Description: A variety of processing operations for high level radioactive waste occur in the High Level Waste Tanks in the H-Area of the Savannah River Site. Thermal design constraints exist on these processes, principally to limit the amount of corrosion inhibitor which must be added to protect the tank and cooling coil materials. The required amount of corrosion inhibitor, which must subsequently be removed prior to trapping the waste in borosilicate glass, increases exponentially with temperature over a… more
Date: October 1, 1992
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uninstrumented assembly airflow testing in the Annular Flow Distribution facility

Description: During the Emergency Cooling System phase of a postulated large-break loss of coolant accident (ECS-LOCA), air enters the primary loop and is pumped down the reactor assemblies. One of the experiments performed to support the analysis of this accident was the Annular Flow Distribution (AFD) experiment, conducted in a facility built for this purpose at Babcock and Wilcox Alliance Research Center in Alliance, Ohio. As part of this experiment, a large body of airflow data were acquired in a protot… more
Date: February 1, 1992
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Flow regime mapping of vertical two-phase downflow in a ribbed annulus

Description: Two-phase flow regimes have been mapped for vertical, cocurrent downflow in a narrow annulus which is partially segmented by the presence of longitudinal ribs. This geometry and flow condition has application to the analysis of a Large-Break Loss of Coolant Accident (LB-LOCA) in the production K-Reactor at the Savannah River Site (SRS). The ribbed annular geometry, particularly the presence of non-sealing ribs, gives rise to some unique phenomenological features. The flow behavior is influenced… more
Date: January 1, 1992
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

ITP. FOR: A code to calculate thermal transients in High Level Waste Tanks

Description: A variety of processing operations for high level radioactive waste occur in the High Level Waste Tanks in the H-Area of the Savannah River Site. Thermal design constraints exist on these processes, principally to limit the amount of corrosion inhibitor which must be added to protect the tank and cooling coil materials. The required amount of corrosion inhibitor, which must subsequently be removed prior to trapping the waste in borosilicate glass, increases exponentially with temperature over a… more
Date: October 1, 1992
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The long-term acceleration of waste glass corrosion: A preliminary review

Description: Whereas a prior conception of glass dissolution assumed a relatively rapid initial dissolution which then slowed to a smaller, fairly constant longer-term rate, some recent work suggests that these two stages are followed by a third phase of dissolution, in which the dissolution rate is accelerated with respect to what had previously been thought of as the final long-term rate. The goals of the present study are to compile experimental data which may have a bearing on this phenomena, and to pro… more
Date: July 1, 1995
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Durability of Defense Waste Processing Facility glasses within the Purex range of compositions

Description: Processing in the Defense Waste Processing Facility (DWPF) is controlled by constraints on predicted properties of the product glass. One of these properties is chemical durability, which is measured as the response of various glass constituents to the seven-day Product Consistency Test (PCT) [1]. As currently implemented into the DWPF`s Product Composition Control System (PCCS) the response of boron is taken as representative of all of the constituent responses, and control is in terms of the … more
Date: May 1, 1995
Creator: Edwards, T. B. & Kielpinski, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion assessment of refractory materials for high temperature waste vitrification

Description: A variety of vitrification technologies are being evaluated to immobilize radioactive and hazardous wastes following years of nuclear materials production throughout the Department of Energy (DOE) complex. The compositions and physical forms of these wastes are diverse ranging from inorganic sludges to organic liquids to heterogeneous debris. Melt and off-gas products can be very corrosive at the high temperatures required to melt many of these waste streams. Ensuring material durability is req… more
Date: November 1995
Creator: Marra, J. C.; Congdon, J. W. & Kielpinski, A. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

GAM-HEAT -- a computer code to compute heat transfer in complex enclosures. Revision 1

Description: The GAM-HEAT code was developed for heat transfer analyses associated with postulated Double Ended Guillotine Break Loss Of Coolant Accidents (DEGB LOCA) resulting in a drained reactor vessel. In these analyses the gamma radiation resulting from fission product decay constitutes the primary source of energy as a function of time. This energy is deposited into the various reactor components and is re- radiated as thermal energy. The code accounts for all radiant heat exchanges within and leaving… more
Date: February 1, 1991
Creator: Cooper, R. E.; Taylor, J. R.; Kielpinski, A. L. & Steimke, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Annular Flow Distribution test. Final report

Description: This report documents the Babcock and Wilcox (B&W) Annular Flow Distribution testing for the Savannah River Laboratory (SRL). The objective of the Annular Flow Distribution Test Program is to characterize the flow distribution between annular coolant channels for the Mark-22 fuel assembly with the bottom fitting insert (BFI) in place. Flow rate measurements for each annular channel were obtained by establishing ``hydraulic similarity`` between an instrumented fuel assembly with the BFI removed … more
Date: December 1, 1990
Creator: Kielpinski, A. L.; Childerson, M. T.; Knoll, K. E.; Manolescu, M. I. & Reed, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of Plasma Vitrification Technology for Contaminated Soil at the Savannah River Site

Description: The Mixed Waste Integrated Program (MWIP) of the United States Department of Energy`s Office of Technology Development is developing treatment technologies for a wide variety of materials containing mixed low-level waste, i.e., having low levels of radioactivity along with hazardous constituents. Vitrification is a promising treatment technology for many of these wastes, including contaminated soil such as that found at the Savannah River Site. Proof-of-principle tests were performed to demonst… more
Date: March 1, 1995
Creator: Kielpinski, A. L.; Marra, J. C.; Rogers, V.; Schumacher, R. F.; Etheridge, J. & Kirkland, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development of a Transportable Vitrification System for Mixed Waste

Description: The US DOE through the Mixed Waste Integrated Program, has identified a need to move mixed waste vitrification technology from the laboratory to the field as rapidly as possible. A great deal of work over the last few years has shown the feasibility of immobilizing selected hazardous waste streams in a vitrified product. Lab-scale work has been extended to pilot-scale tests, usually with surrogates of the actual waste. DOE felt that the technology was mature enough to allow demonstration in the… more
Date: January 13, 1995
Creator: Whitehouse, J. C.; Jantzen, Carol M.; Bickford, D. F.; Kielpinski, A. L.; Helton, B. D. & Van Ryn, F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

High-temperature vitrification of low-level radioactive and hazardous wastes

Description: The US Department of Energy (DOE) weapons complex has numerous radioactive waste streams which cannot be easily treated with joule-heated vitrification systems. However, it appears these streams could be treated With certain robust, high-temperature, melter technologies. These technologies are based on the use of plasma torch, graphite arc, and induction heating sources. The Savannah River Technology Center (SRTC), with financial support from the Department of Energy, Office of Technology Devel… more
Date: December 1, 1995
Creator: Schumacher, R. F.; Kielpinski, A. L.; Bickford, D. F.; Cicero, C. A.; Applewhite-Ramsey, A.; Spatz, T. L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Annular Flow Distribution test

Description: This report documents the Babcock and Wilcox (B W) Annular Flow Distribution testing for the Savannah River Laboratory (SRL). The objective of the Annular Flow Distribution Test Program is to characterize the flow distribution between annular coolant channels for the Mark-22 fuel assembly with the bottom fitting insert (BFI) in place. Flow rate measurements for each annular channel were obtained by establishing hydraulic similarity'' between an instrumented fuel assembly with the BFI removed an… more
Date: December 1, 1990
Creator: Kielpinski, A.L. (ed.) (Westinghouse Savannah River Co., Aiken, SC (United States)); Childerson, M.T.; Knoll, K.E.; Manolescu, M.I. & Reed, M.J. (Babcock and Wilcox Co., Alliance, OH (United States). Research Center)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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