1,018 Matching Results

Search Results

Advanced search parameters have been applied.

Knock-limited power outputs from a CFR engine using internal coolants 3: four alkyl amines, three alkanolamines six amides, and eight heterocyclic compounds

Description: Report presenting investigations to determine the antiknock effectiveness of various additive-water solutions used as internal coolants in conjunction with AN-F-28, Amendment-2, fuel in a modified CFR engine.
Date: February 3, 1947
Creator: Imming, Harry S. & Bellman, Donald R.
Partner: UNT Libraries Government Documents Department

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.
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.
Partner: UNT Libraries Government Documents Department

Some Effects of Internal Coolants on Knock-Limited and Temperature-Limited Power as Determined in a Single-Cylinder Aircraft Test Engine

Description: Report presenting an investigation to determine the permissible increase in engine power by using various internal coolants from the consideration of fuel knock and cylinder cooling. The internal coolants tested were water, 30-70 methyl alcohol-water volume percent mixture, 70-30 methyl alcohol-water volume percent mixture, methyl alcohol, and 80-20 ethyl alcohol-water volume percent mixture.
Date: August 1944
Creator: Wear, Jerrold D.; Held, Louis F. & Slough, James W.
Partner: UNT Libraries Government Documents Department

Heat-Transfer Tests of Several Engine Coolants

Description: Report presenting the relative cooling performance of water, commercial Prestone, and several ethylene-glycol and diethylene-glycol derivatives obtained from tests conducted with a small electrically heated heat exchanger.
Date: February 1945
Creator: Manganiello, E. J. & Stalder, J. R.
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.
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.
Partner: UNT Libraries Government Documents Department

Investigation of Lithium Hydride and Magnesium as High-Temperature Internal Coolants With Several Skin Materials

Description: Memorandum presenting an investigation of hemispherical nose shapes of titanium, stainless steel coated with aluminum oxide, and uncoated stainless steel with lithium hydride and magnesium as internal coolants. Results regarding titanium models, stainless-steel models (uncoated), stainless-steel models coated with aluminum oxide, solution effects on the decomposition temperature of lithium hydride, effect of lithium hydride and magnesium on temperature measurements, and efficiency of models cooled with lithium hydride are provided.
Date: May 28, 1958
Creator: Modisette, Jerry L.
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.
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.
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
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
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.
Partner: UNT Libraries Government Documents Department

Sequential charged-particle and neutron activation of Flibe in the HYLIFE-II inertial fusion energy power plant design

Description: Most radionuclide generation/depletion codes consider only neutron reactions and assume that charged particles, which may be generated in these reactions, deposit their energy locally without undergoing further nuclear interactions. Neglect of sequential charged-particle (x,n) reactions can lead to large underestimation in the inventories of radionuclides. PCROSS code was adopted for use with the ACAB activation code to enable calculation of the effects of (x,n) reactions upon radionuclide inventories and inventory-related indices. Activation calculations were made for Flibe (2LiF + BeF{sub 2}) coolant in the HYLIFE-II inertial fusion energy (IFE) power plant design. For pure Flibe coolant, it was found that (x,n) reactions dominate the residual contact dose rate at times of interest for maintenance and decommissioning. For impure Flibe, however, radionuclides produced directly in neutron reaction dominate the contact dose rate and (x,n) reactions do not make a significant contribution. Results demonstrate potential importance of (x,n) reactions and that the relative importance of (x,n) reactions varies strongly with the composition of the material considered. Future activation calculations should consider (x,n) reactions until a method for pre-determining their importance is established.
Date: June 14, 1996
Creator: Latkowski, J.F.; Tobin, M.T.; Vujic, J.L. & Sanz, J.
Partner: UNT Libraries Government Documents Department

Precise Measurement of Process Temperature Differences

Description: Measurement of power in a nuclear reactor system is comparable to measurement of yield in a chemical plant or to measurement of throughput in a paper mill process. In most reactor systems power is determined by measurement of heat transferred to the coolant. In this study reactor coolant heat-rise was determined by the differential-temperature measuring circuitry of a power calculator which computed and recorded reactor power. This paper presents measurement techniques involved in determining the differential temperature and may be of parallel interest to instrument engineers in other process fields.
Date: January 16, 2003
Creator: Kitchen, B.G.
Partner: UNT Libraries Government Documents Department

APT Blanket Safety Analysis: Preliminary Analyses of Downflow Through a Lateral Row 1 Blanket Model Under Near RHR Conditions

Description: To address a concern about a potential maldistribution of coolant flow through an APT blanket module under low flow near RHR conditions, a scoping study of downflow mixed convection in parallel channels was conducted. Buoyancy will adversely effect the flow distribution in module bins with downflow and non-uniform power distributions. This study consists of two parts: a simple analytical model of flow in a two channel network, and a lumped eleven channel FLOWTRAN-TF model of a front lateral Row-1 blanket module bin. Results from both models indicate that the concern about coolant flow in a vertical model being diverted away from high power regions by buoyancy is warranted. The FLOWTRAN-TF model predicted upflow (i.e., a flow reversal) through several of the high power channels, under some low flow conditions. The transition from the regime with downflow in all channels to a regime with upflow in some channels was abrupt.
Date: October 7, 1998
Creator: Hamm, L. L.
Partner: UNT Libraries Government Documents Department

Modeling of water radiolysis at spallation neutron sources

Description: In spallation neutron sources neutrons are produced when a beam of high-energy particles (e.g., 1 GeV protons) collides with a (water-cooled) heavy metal target such as tungsten. The resulting spallation reactions produce a complex radiation environment (which differs from typical conditions at fission and fusion reactors) leading to the radiolysis of water molecules. Most water radiolysis products are short-lived but extremely reactive. When formed in the vicinity of the target surface they can react with metal atoms, thereby contributing to target corrosion. The authors describe the results of calculations and experiments performed at los alamos to determine the impact on target corrosion of water radiolysis in the spallation radiation environment. The computational methodology relies on the use of the Los Alamos radiation transport code, LAHET, to determine the radiation environment, and the AEA code, FACSIMILE, to model reaction-diffusion processes.
Date: December 1, 1998
Creator: Daemen, L.L.; Kanner, G.S.; Lillard, R.S.; Butt, D.P.; Brun, T.O. & Sommer, W.F.
Partner: UNT Libraries Government Documents Department