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Calibration of a drag disc turbine transducer and a gamma beam densitometer to measure the mass flow rate in separated horizontal two-phase flow

Description: The accurate measurement of two-phase mass flow rate is very important in experiments, such as the LOFT experiment, which investigate the hypothetical Loss-of-Coolant Accident (LOCA). This paper analyzes experiments designed to determine the behavior of a LOFT free field drag disc turbine transducer (DTT) and a LOFT-type three-beam gamma densitometer in a steady state, horizontal high pressure steam-water flow. The experiments were conducted in a mass flow and void fraction range where a variet… more
Date: January 1, 1979
Creator: Reimann, J. & Solbrig, C.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Simplified probabilistic risk assessment in fuel reprocessing

Description: An evaluation was made to determine if a backup mass tracking computer would significantly reduce the probability of criticality in the fuel reprocessing of the Integral Fast Reactor. Often tradeoff studies, such as this, must be made that would greatly benefit from a Probably Risk Assessment (PRA). The major benefits of a complete PRA can often be accrued with a Simplified Probabilistic Risk Assessment (SPRA). An SPRA was performed by selecting a representative fuel reprocessing operation (mov… more
Date: January 1, 1993
Creator: Solbrig, C.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Simplified probabilistic risk assessment in fuel reprocessing

Description: An evaluation was made to determine if a backup mass tracking computer would significantly reduce the probability of criticality in the fuel reprocessing of the Integral Fast Reactor. Often tradeoff studies, such as this, must be made that would greatly benefit from a Probably Risk Assessment (PRA). The major benefits of a complete PRA can often be accrued with a Simplified Probabilistic Risk Assessment (SPRA). An SPRA was performed by selecting a representative fuel reprocessing operation (mov… more
Date: March 1, 1993
Creator: Solbrig, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Heat release rate from the combustion of uranium

Description: Fuel treatment is planned at the Argonne National Laboratory on EBR-II spent fuel. The electrochemical treatment process is carried out in a cell with an argon atmosphere to prevent any reaction. The amount of fuel processed at any time is limited by the amount of energy which could be released by metal combustion if air is inadvertently allowed into the cell since the heat release would increase the cell pressure. The cell pressure is required to be below atmospheric even if combustion occurs … more
Date: July 1995
Creator: Solbrig, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Minimization of heat slab nodes with higher order boundary conditions

Description: The accuracy of a numerical solution can be limited by the numerical approximation to the boundary conditions rather than the accuracy of the equations which describe the interior. The study presented in this paper compares the results from two different numerical formulations of the convective boundary condition on the face of a heat transfer slab. The standard representation of the boundary condition in a test problem yielded an unacceptable error even when the heat transfer slab was partitio… more
Date: January 1, 1992
Creator: Solbrig, C.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Minimization of heat slab nodes with higher order boundary conditions

Description: The accuracy of a numerical solution can be limited by the numerical approximation to the boundary conditions rather than the accuracy of the equations which describe the interior. The study presented in this paper compares the results from two different numerical formulations of the convective boundary condition on the face of a heat transfer slab. The standard representation of the boundary condition in a test problem yielded an unacceptable error even when the heat transfer slab was partitio… more
Date: December 1, 1992
Creator: Solbrig, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Performance evaluation of a drag-disc turbine transducer and three-beam gamma densitometer under transient two-phase flow conditions

Description: One of the primary variables measured in the Loss-of-Fluid Test (LOFT) Program is mass flow rate. LOFT uses drag-disc turbine tranducers (DTT) and a three-beam gamma densitometer to measure parameters from which mass flow may be computed. The transducer combination was performance tested under transient conditions in the blowdown loop at the LOFT Test Support Facility (LTSF). The performance tests consisted of three partial blowdowns of different durations starting from the same initial conditi… more
Date: January 1, 1979
Creator: Nalezny, C L; Chen, L L & Solbrig, C W
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Determination of the shape of a plutonium deposit from a leaking crucible

Description: An analytical model was developed which predicts that the leak rate (or drip rate) of molten plutonium onto a substrate must be low in order for plutonium to solidify into a problematical hemispherical shape. The heat transfer to the substrate is the significant factor in how quickly the fuel solidifies. Analysis and experiment show that for a given substrate, the deposit center height is independent of the leakrate. A good conductor, such as copper on the bottom of a fuel casting furnace, will… more
Date: January 1, 1993
Creator: Solbrig, C.W. & Clarksean, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

LOFT fuel rod surface temperature measurement testing

Description: Testing of the LOFT fuel rod cladding surface thermocouples has been performed to evaluate how accurately the LOFT thermocouples measure the cladding surface temperature during a loss-of-coolant accident (LOCA) sequence and what effect, if any, the thermocouple would have on core performance. Extensive testing has been done to characterize the thermocouple design. Thermal cycling and corrosion testing of the thermocouple weld design have provided an expected lifetime of 6000 hours when exposed … more
Date: January 1, 1978
Creator: Eaton, A. M.; Tolman, E. L. & Solbrig, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

LOFT fuel rod thermal/mechanical behavior predictions

Description: Best-estimate predictions of LOFT fuel rod behavior during the first LOFT nuclear test series have been made with both RELAP/FLOOD4/FRAP-T and RELAP/SCORE/MOXY computer code combinations. The purpose of the predictions are to test the best-estimate code accuracy by comparison of predictions to subsequent test data and to develop plans for post-test fuel replacements and examinations. The FRAP-T3 computer code was utilized which couples the thermal, mechanical, internal gas, and material propert… more
Date: January 1, 1978
Creator: Niebruegge, D. A.; Tolman, E. L. & Solbrig, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Determination of the shape of a plutonium deposit from a leaking crucible

Description: An analytical model was developed which predicts that the leak rate (or drip rate) of molten plutonium onto a substrate must be low in order for plutonium to solidify into a problematical hemispherical shape. The heat transfer to the substrate is the significant factor in how quickly the fuel solidifies. Analysis and experiment show that for a given substrate, the deposit center height is independent of the leakrate. A good conductor, such as copper on the bottom of a fuel casting furnace, will… more
Date: March 1, 1993
Creator: Solbrig, C. W. & Clarksean, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

LOFT: a nuclear plant providing realistic answers to PWR licensing issues

Description: This paper discusses the role the Loss-of-Fluid Test (LOFT) Experimental Program has played and will play in addressing licensing issues of interest to the US Nuclear Regulatory Commission (NRC), nuclear steam supply system vendors, and utility power companies. The LOFT facility is an operating, prototypically scaled pressurized water reactor (PWR) system in which experiments are performed that characterize conditions for postulated accidents in a commercial PWR. The accident conditions imposed… more
Date: January 1, 1980
Creator: Solbrig, C.W.; Linebarger, J.H. & Kaufman, N.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Characteristics and stability analyses of transient one-dimensional two- phase flow equations and their finite difference approximations

Description: Equation systems describing one-dimensional, transient, two-phase flow with separate continuity, momentum, and energy equations for each phase are classified by use of the method of characteristics. Little attempt is made to justify the physics of these equations. Many of the equation systems possess complex-valued characteristics and hence, according to well-known mathematical theorems, are not well-posed as initial-value problems (IVPs). Real-valued characteristics are necessary but not suffi… more
Date: January 1, 1975
Creator: Lyczkowski, R. W.; Gidaspow, D.; Solbrig, C. W. & Hughes, E. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

TREAT (Transient Reactor Test Facility) reactor control rod scram system simulations and testing

Description: Air cylinders moving heavy components (100 to 300 lbs) at high speeds (above 300 in/sec) present a formidable end-cushion-shock problem. With no speed control, the moving components can reach over 600 in/sec if the air cylinder has a 5 ft stroke. This paper presents an overview of a successful upgrade modification to an existing reactor control rod drive design using a computer model to simulate the modified system performance for system design analysis. This design uses a high speed air cylind… more
Date: January 1, 1990
Creator: Solbrig, C. W. & Stevens, W. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Glovebox heat test.

Description: An existing argon atmosphere glovebox enclosure was to be refurbished for contaminated operations with a large, high temperature induction furnace. Thermal modeling indicated that glovebox temperatures would be high but acceptable without active cooling, but there were significant concerns that the analysis was inadequate and active cooling would be required. In particular, radiant heating of the glovebox walls by the furnace and pressure control system performance were concerns the thermal mod… more
Date: August 21, 2002
Creator: Bushnell, C. G.; Rigg, R. H. & Solbrig, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Pyrophoricity of uranium in long-term storage environments

Description: A corrosion cycle for uranium is postulated which can be used to assess whether a given storage situation might produce fire hazards and/or continual uranium corrosion. A significant reaction rate of uranium and moisture occurs at room temperature which produces uranium oxide and hydrogen. If the hydrogen cannot escape, it will react slowly with uranium to form uranium hydride. The hydride is pyrophoric at room temperature when exposed to air. Either the hydrogen or the hydride can produce a da… more
Date: January 1, 1994
Creator: Solbrig, C W; Krsul, J R & Olsen, D N
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Performance assessment of mass flow rate measurement capability in a large scale transient two-phase flow test system

Description: Mass flow is an important measured variable in the Loss-of-Fluid Test (LOFT) Program. Large uncertainties in mass flow measurements in the LOFT piping during LOFT coolant experiments requires instrument testing in a transient two-phase flow loop that simulates the geometry of the LOFT piping. To satisfy this need, a transient two-phase flow loop has been designed and built. The load cell weighing system, which provides reference mass flow measurements, has been analyzed to assess its capability… more
Date: January 1, 1979
Creator: Nalezny, C L; Chapman, R L; Martinell, J S; Riordon, R P & Solbrig, C W
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Transient three-dimensional thermal-hydraulic analysis of nuclear reactor fuel rod arrays: general equations and numerical scheme

Description: A mathematical model and a numerical solution scheme for thermal- hydraulic analysis of fuel rod arrays are given. The model alleviates the two major deficiencies associated with existing rod array analysis models, that of a correct transverse momentum equation and the capability of handling reversing and circulatory flows. Possible applications of the model include steady state and transient subchannel calculations as well as analysis of flows in heat exchangers, other engineering equipment, a… more
Date: November 1, 1975
Creator: Wnek, W.J.; Ramshaw, J.D.; Trapp, J.A.; Hughes, E.D. & Solbrig, C.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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