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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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239 records · Page 14

Tracer Methods for Characterizing Fracture Creation in Engineered Geothermal Systems

The aim of this proposal is to develop, through novel high-temperature-tracing approaches, three technologies for characterizing fracture creation within Engineered Geothermal Systems (EGS). The objective of a first task is to identify, develop and demonstrate adsorbing tracers for characterizing interwell reservoir-rock surface areas and fracture spacing. The objective of a second task is to develop and demonstrate a methodology for measuring fracture surface areas adjacent to single wells. The objective of a third task is to design, fabricate and test an instrument that makes use of tracers for measuring fluid flow between newly created fractures and wellbores. In one method of deployment, it will be used to identify qualitatively which fractures were activated during a hydraulic stimulation experiment. In a second method of deployment, it will serve to measure quantitatively the rate of fluid flowing from one or more activated fracture during a production test following a hydraulic stimulation.

15 GEOTHERMAL ENERGY↗

Measuring the Increment in the Free Volume of Composite Components

Various methods of measuring the increment in the free volume of composite components are considered, so as to assess which is most suitable for automation of such measurements as a function of the pressure within the component. A method permitting such measurements with high precision is found, and the corresponding instrument is described.

42 ENGINEERING↗

Coefficients of Flow of Standard Nozzles

We first undertook experiments with air, devoted principally to the investigation of the disturbances due to the differences in the nature of the flow to the nozzle. The difficulty of measuring the air, however, caused us to experiment with water. Due to the possibility of measuring the capacity of the container, this method was much more accurate than measuring with Pitot tobes.

FLOWMETERS, GAGES, ETC↗

Experimental Activities with the IELLLO Lithium-Lead Facility

Fusion power offers the prospect of an almost inexhaustible source of energy for future generations. Although this may be true, it also presents so far serious scientific and engineering challenges. Breeding Blanket is one of key components of future fusion reactors, since it directly involves tritium breeding and energy extraction, both of them critical to development of fusion power. To deal with the development of Breeding Blankets, ENEA (Italian National Agency for New Technologies, Energy and Sustainable Economic Development) designed and built a lead lithium loop (IELLLO: Integrated European Lead Lithium Loop): the experiment aims to support R and D activities for the conceptual and preliminary design of the European test blanket systems. IELLLO was completed, installed and operated at ENEA Brasimone Research Centre. The purpose of this work is to describe the experimental activities that have been carried out concerning the qualification of the facility, and relative instrumentations, for lead lithium applications. A series of thermo-hydraulic investigations on IELLLO facility has been elaborated: lead lithium pressure transducers, heat exchanger, permanent magnet pumping system, mass flow meters and air cooler have been tested. The absolute pressure meter in contact with Pb-16Li was qualified in pressure range up to 10 bar and temperature up to 400 deg. C. The installation of new kinds of Pb-16Li differential pressure transducers will allow to check the pump characteristic curve and accurately calculate valves pressure drops. These factors could give a better information for the thermo-hydraulic qualification of the facility. Vortex Mass Flow Meter has shown good results in terms of accuracy. The performance has been validated by thermal balance with a dedicated heating system. Nevertheless, the installations of different types of mass flow meters will enable to test IELLLO at ITER relevant conditions, and at lower mass flow rates than those tested up to now. The new pumping system with a PM Pump, was qualified for the first time in Pb-16Li, and the procedure for the operation and maintenance of the pump was developed. The pump is able to supply a mass flow rate in the range from 1.2 to 2.4 kg/s with a temperature of Pb-16Li up to 550 deg. C in the test section. Significant results have been obtained also for the heat exchanger, which has shown high efficiencies, even more than expected. Likewise, the Air Cooler has been verified to be able to cool Pb-16Li in a relatively short time, even at the worst temperature and mass flow conditions. (authors)

42 ENGINEERING↗

Primary coolant flow measurement for integral pressurized water reactors using ultrasonic technique - 182

Several pressurized water reactor (PWR) systems under development employ integral primary coolant loop designs, where the primary coolant does not leave the reactor pressure vessel during operation (I{sup 2}S-LWR, mPower, NuScale). The absence of primary coolant piping inhibits traditional pressurized water reactor primary coolant flow measurement, in which the differential pressure across the steam generator is correlated to flow rate. To address this, a transit time, reflection mode, ultrasonic flow meter is proposed. An experimental flow loop utilizing a test section representative of a thin azimuthal slice of the down-comer region of an integral PWR has been constructed to test the efficacy of the General Electric AT600 ultrasonic flow meter (UFM) in such an application. A Great Plains Industries TM300 turbine flow meter (TFM), reporting volumetric flow rate and installed in-line with the flow loop piping, is used as the reference meter. UFM performance is affected by several factors, including flow development and symmetry. The UFM was installed on three locations along the flow path of water through the test section. The meter performed the best at the downstream end of the test section, where the fluid flow is the most developed. Performance, measured by percent error in UFM average reading with respect to the TFM average reading, generally improved with increasing flow rate at all locations, though absolute difference between meter readings increased with flow rate. This research suggests that ultrasonic approaches hold promise for non-invasive measurement of primary coolant flow in integral PWRs. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗