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Knock-limited performance of several internal coolants

Description: The effect of internal cooling on the knock-limited performance of an-f-28 fuel was investigated in a CFR engine, and the following internal coolants were used: (1) water, (2), methyl alcohol-water mixture, (3) ammonia-methyl alcohol-water mixture, (4) monomethylamine-water mixture, (5) dimethylamine-water mixture, and (6) trimethylamine-water mixture. Tests were run at inlet-air temperatures of 150 degrees and 250 degrees F. to indicate the temperature sensitivity of the internal-coolant solutions.
Date: February 1, 1944
Creator: Bellman, Donald R. & Evvard, John C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Knock-limited power outputs from a CFR engine using internal coolants 1: monomethylamine and dimethylamine

Description: Report presenting an investigation to determine the knock-limited power obtainable by injecting water solutions of monomethylamine and dimethylamine as internal coolants into a CFR engine using AN-F-28, Amendment-2, fuel.
Date: December 1944
Creator: Bellman, Donald R.; Moeckel, W. E. & Evvard, John C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Preliminary survey of possible methods for hypersonic aircraft

Description: Report presenting an investigation conducted to determine the relative advantages and limitations of a number of fluids for use as either heat sinks or coolants for hypersonic aircraft. The feasibility of the fluids tested as heat sinks and cooling in the high-level and low-level regions is described.
Date: May 12, 1958
Creator: Esgar, Jack B.; Hickel, Robert O. & Stepka, Francis S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

An estimation of the internal-cooling requirements of an aircraft-engine cylinder when using oxygen boost

Description: Report discusses a method developed to estimate the quantities of internal coolants required to prevent overheating of the aircraft cylinder when oxygen boost is applied. The formula and calculations related to inlet-air pressure, added oxygen, added water, added nitrogen, and total fluid weight are detailed.
Date: November 1944
Creator: Evvard, John C. & Moeckel, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

The Effectiveness of Spray Cooling

Description: Abstract: "A possible method of cooling a liquid-fuel reactor is by spraying liquid metal through the liquid fuel, and then circulating the liquid metal through a heat exchanger. To evaluate the effectiveness of this cooling method, a few simple experiments were made with mercury sprayed through water. On the basis of the results, it was concluded that this method was intrinsically a low-power-density method, which could not find application except where a low fissionable-material inventory was the dominating requirement in a low-power reactor. Even there, it is thought that a boiling homogeneous reactor might be superior. The results are reported, in spite of their probably lack of value in the reactor program, simply to make the record complete."
Date: October 1, 1953
Creator: Dayton, R. W.; Allen, C. M. & Miller, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

SUBCONTRACT REPORT: DC-DC Converter for Fuel Cell and Hybrid Vehicles

Description: The goal of this project is to develop and fabricate a 5kW dc-dc converter with a baseline 14V output capability for fuel cell and hybrid vehicles. The major objectives for this dc-dc converter technology are to meet: Higher efficiency (92%); High coolant temperature,e capability (105 C); High reliability (15 Years/150,000miles); Smaller volume (5L); Lower weight (6kg); and Lower cost ($75/kW). The key technical challenge for these converters is the 105 C coolant temperatures. The power switches and magnetics must be designed to sustain these operating temperatures reliably, without a large cost/mass/volume penalty.
Date: July 1, 2007
Creator: Marlino, Laura D & Zhu, Lizhi
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Flow boiling test of GDP replacement coolants

Description: The tests were part of the CFC replacement program to identify and test alternate coolants to replace CFC-114 being used in the uranium enrichment plants at Paducah and Portsmouth. The coolants tested, C{sub 4}F{sub 10} and C{sub 4}F{sub 8}, were selected based on their compatibility with the uranium hexafluoride process gas and how well the boiling temperature and vapor pressure matched that of CFC-114. However, the heat of vaporization of both coolants is lower than that of CFC-114 requiring larger coolant mass flow than CFC-114 to remove the same amount of heat. The vapor pressure of these coolants is higher than CFC-114 within the cascade operational range, and each coolant can be used as a replacement coolant with some limitation at 3,300 hp operation. The results of the CFC-114/C{sub 4}F{sub 10} mixture tests show boiling heat transfer coefficient degraded to a minimum value with about 25% C{sub 4}F{sub 10} weight mixture in CFC-114 and the degree of degradation is about 20% from that of CFC-114 boiling heat transfer coefficient. This report consists of the final reports from Cudo Technologies, Ltd.
Date: August 1, 1995
Creator: Park, S.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Diamond Wire Cutting of the Tokamak Fusion Test Reactor

Description: The Tokamak Fusion Test Reactor (TFTR) is a one-of-a-kind, tritium-fueled fusion research reactor that ceased operation in April 1997. As a result, decommissioning commenced in October 1999. The 100 cubic meter volume of the donut-shaped reactor makes it the second largest fusion reactor in the world. The deuterium-tritium experiments resulted in contaminating the vacuum vessel with tritium and activating the materials with 14 MeV neutrons. The total tritium content within the vessel is in excess of 7,000 Curies, while dose rates approach 50 mRem/hr. These radiological hazards along with the size of the tokamak present a unique and challenging task for dismantling. Engineers at the Princeton Plasma Physics Laboratory (PPPL) decided to investigate an alternate, innovative approach for dismantlement of the TFTR vacuum vessel: diamond wire cutting technology. In August 1999, this technology was successfully demonstrated and evaluated on vacuum vessel surrogates. Subsequently, the technology was improved and redesigned for the actual cutting of the vacuum vessel. Ten complete cuts were performed in a 6-month period to complete the removal of this unprecedented type of D&D (Decontamination and Decommissioning) activity.
Date: January 31, 2003
Creator: Rule, Keith; Perry, Erik & Parsells, Robert
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Monte Carlo treatment of heat flow through a neutral gas layer

Description: From surface effects in controlled thermonuclear fusion devices and reactors meeting; Argonne, Illinois, USA (10 Jan 1974). The flow of heat through a neutral gas layer under conditions of density and temperature relevant to the cooling layer used in a reference theta-pinch reactor (RTPR) was investigated numerically by means of a Monte Carlo technique. The necessity for corrections to the fluid model was indicated and assessed in an example calculation. (auth)
Date: January 1, 1973
Creator: Oliphant, T.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department

SN5001-AN IBM-650 CODE FOR STEADY-STATE THERMAL EVALUATION OF AN INSTRUMENTED MULTIFUEL-PLATE SUBASSEMBLY

Description: An IBM-650 computer program, SN5001, for the calculation of steady-state thermal conditions in the fuel plates and coolant of an instrumented multi-fuel- plate subassembly is described. The program is applicable for subcooled or bulk boiling coolant conditions and surface conditions of heating, local boiling, and film boilimg, and can be used for data reduction or design. The derivation and a list of the heat conduction and coolant enthalpy equations and a description of the code sufficient for its use are contained. (auth)
Date: April 1, 1960
Creator: Arbtin, E. & Westphal, R.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT COOLANT DISTRIBUTION TESTS. Final Report

Description: Tests were made to determine the head loss coefficient through the inlet plenum of the Pathfinder reactor and to determine the now distribution among the fuel element nozzles for various operating conditions--with all three pumps operating at the same flow rate and with any combination of only two pumps operating at the same flow rate. A quarter-scale wooden model was used for the tests. Air was used as the fluld. The loss coefficient was determined to be 1.8 plus or minus 0.3. The velocities of flow through the fuel element nozzles were determined to be within plus or minus 5 per cent of average flow when all pumps are operating and within plus or minus 10 per cent of average flow when only two pumps are operating. (auth)
Date: November 15, 1959
Creator: Wilson, J. & Styles, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

PERFORMANCE TEST OF A TWO-COOLANT-REGION SODIUM PUMP SHAFT FREEZE-SEAL

Description: The operation of the freeze-seal type sodium pump requires a shaft freeze-seal capable of retaining sodium. A prototype two-coolant-region freeze seal for application on HNPF sodium pumps was designed and constructed. It was tested under environmental conditions to determine its operating characteristics and sodium retaining capabilities. (auth)
Date: July 15, 1959
Creator: Streck, F.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Elastic Metal Alloy Refrigerants

Description: Advanced Research Projects Agency-Energy project sheet summarizing general information about the Building Energy Efficiency Through Innovative Thermodevices (BEETIT) program including critical needs, innovation and advantages, impacts, and contact information. This sheet discusses air conditioning with more efficient cooling systems as part of the "Thermoelastic Cooling" project.
Date: February 15, 2012
Creator: University of Maryland
Item Type: Refine your search to only Text
Partner: UNT Libraries Government Documents Department

Neutron Cross Section Uncertainties in the Thermal and Resonance Regions

Description: In the 'Atlas of Neutron Resonances', special care was expended to ensure that the resonance parameter information reproduces the various measured thermal cross sections, as well as the infinite dilute resonance integrals for Z = 1-100. In contrast, the uncertainties of the recommended quantities do not match those generated from the uncertainties of the resonance parameters. To address this problem, the present study was initiated to achieve consistency for 15 actinides and 21 structural and coolant moderator materials. This is realized by assigning uncertainties to the parameters of the negative-energy resonances and changing, if necessary, significantly the uncertainties of the low-lying positive-energy resonances. The influence of correlations between parameters on the derived uncertainties is examined and discussed.
Date: June 24, 2008
Creator: Mughabghab,S.F. & Oblozinsky, P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department

Strees Corrosion Cracking Initiation of Ni-Bassed Alloys in High Temperature Water

Description: The goal of the work is to provide stress corrosion cracking (SCC) initiation data for Alloy 600 that is not compromised by (1) specimens that suffer from stress relaxation, (2) specimens which have an unknown stress state, (3) specimens which are tested at unknown positions electrochemically relative to the Ni/NiO phase transition, and (4) testing which relies on the period of time between specimen inspection intervals to estimate SCC initiation times. The current study was aimed at studying the effects of temperature and coolant hydrogen concentration on SCC initiation in high purity, high temperature water.
Date: March 21, 2005
Creator: Richey, E & Morton, D
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department

Summary Results of the Neptun Boil-Off Experiments to Investigate the Accuracy and Cooling Influence of LOFT Cladding-Surface Thermocouples (System 00)

Description: Nine boil-off experiments were conducted in the Swiss NEPTUN Facility primarily to obtain experimental data for assessing the perturbation effects of LOFT thermocouples during simulated small-break core uncovery conditions. The data will also be useful in assessing computer model capability to predict thermal hydraulic response data for this type of experiment. System parameters that were varied for these experiments included heater rod power, system pressure, and initial coolant subcooling. The experiments showed that the LOFT thermocouples do not cause a significant cooling influence in the rods to which they are attached. Furthermore, the accuracy of the LOFT thermocouples is within 20 K at the peak cladding temperature zone.
Date: October 1, 1981
Creator: Tolman, E. L. & Aksan, S. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

LOFT Monthly Progress Report for March 1980

Description: During March, evaluation of Test L3-2 continued and preparations began for the next tests, L6-5 and L3-7. Test L6-5 is the first test of the operational transient series and is a loss-of-feedwater incident. Test L3-7 is a small break, similar to L3-2, wherein the emergency coolant flow is adjusted to permit investigation of natural circulation modes. The controlling schedule items involve efforts to add instrumentation to the plant to better characterize system response. Specifically, a new hot-leg penetration will be installed and steam generator water level instrumentation will be improved. For March, costs to date agree very well with budget. Efforts are underway to develop a new baseline program for FY-80 and FY-81 based on a revised test plan and recent budget guidance for FY-81. These efforts are targeted for mid-year review in April.
Date: April 1, 1980
Creator: Kaufman, N. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

LOFT Monthly Progress Report for February 1980

Description: The significant event of February was the on-schedule conduct of Test L3-2 on February 7. This was the second LOFT small break test with nuclear heat. It simulated a break of a one-inch pipe in a large commercial plant, whereas Test L3-1 had simulated a break of a four-inch pipe. For Test L3-2, the reactor plant and emergency core cooling system appeared to function as expected, although preliminary data evaluation indicates a higher break flow than expected, with a correspondingly greater depressurization. As the month ended, data evaluation was continuing. During February, Nuclear Regulatory Commission guidance was received that would require Tests L3-5 and L3-6 to use nuclear heat. Previously these tests, the next planned tests, had been designed as nonnuclear tests with and without operating coolant pumps. This revised guidance will require a replanning of the entire program schedule for better facility use. At the end of the month, replanning was underway. Costs for February are right on budget, although manpower levels are somewhat greater than budget. This latter variance results from an intentional manpower-material interchange.
Date: March 1, 1980
Creator: Kaufman, N. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department