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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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At least 721 records · Page 40

High Effectiveness, Compact, High Pressure and Low Cost Recuperator for Super-Critical CO2 Power Cycles, Paper Presented at The Fifth International Symposium – Super-Critical CO2 Power Cycles, San Antonio, Texas, March 28-31, 2016, by Dr. John Kelly, President, Altex Technologies Corporation

Closed Brayton super-critical CO2 power cycles are well suited to waste heat bottoming cycles, due to their increased efficiency and compactness, relative to Rankine steam bottoming cycles. Since waste heat applications would be retrofits, the power system compactness is important. To achieve high efficiency, these power cycles require high pressure recuperative type heat exchangers, of substantial heat duty. Current Printed Circuit Heat Exchangers (PCHE), originally developed for high pressure gas and oil applications, can be used as recuperators, but costs are higher than desired. Altex is developing a purpose-built high pressure and effectiveness recuperator to provide the reliability, compactness, performance and pressure capability of current recuperators, but at a reduced cost. The High Effectiveness Low Cost (HELC) recuperative heat exchanger design yields volume and weight metrics of .0024 m3/UA and 10.2 kg/UA, which are 4% and 77.3% below recuperator target metrics, respectively. A 50 kW test article was designed and fabricated. Performance tests on water and oil showed that the HELC design model could predict heat transfer, to within 10% of the measured value. This model was then used to project HELC performance, when operating on supercritical CO2. Besides performance tests, the test article was hydrostatically tested, for integrity at up to 4,000 psi pressure. At these conditions, some distortion of channels was encountered. To mitigate distortion, the inserts were redesigned and these results were used to project the cost of 500 kW and 5,083 kW HELC units. The cost metric for the 5,083 kW unit was determined to be $1,349/UA, which is 10% lower than the recuperator desired cost metric desired target of $1,500/UA. In addition, the 5,083 kW unit HELC cost of $61.09/kW is 33.6% lower than the $92/kW estimated cost for a PCHE. Hydrostatic pressure tests, at up to 4,000psi, showed that the unit did not leak. However, channels were distorted at this pressure differential. Design updates to minimize stress concentrations and distortion were prepared and analyzed, to show that distortion could be controlled, but to date tests have not been run to prove the design. Project results show the potential of the HELC approach, but more work is required to confirm this potential, at the larger scales of interest.

14 SOLAR ENERGY↗

Radionuclide Migration at a Plowshare Program Site: the Gasbuggy Underground Nuclear Test Site, San Juan County, New Mexico - 17019

Project Gasbuggy in northwest New Mexico was the first of three subsurface nuclear tests the U.S. Atomic Energy Commission conducted to evaluate the potential to enhance the production of natural gas from low-permeability geologic formations. In 1967, a 29-kiloton nuclear device was detonated in the Lewis Shale (marine shale and siltstone), 1,292 m below the land surface. The detonation vaporized a cavity into which overlying rock collapsed, forming a 101-m high rubble-filled chimney with a radius of 25 m. Explosion-generated fractures extended between 120 m and 150 m from the working point (detonation location). Most of the radionuclides generated from the explosion remain in the cavity melt glass or have decayed to negligible amounts; tritium radioactivity, however, is still high enough and potentially mobile enough to be of concern. Tritium is able to exchange with stable hydrogen and form liquid water and water vapor; under two-phase (liquid and gas) reservoir conditions the majority of tritium is stored as liquid water and volatilises only to restore equilibrium conditions as gas is removed. A numerical model was developed to examine the migration of tritium in both phases through the fractured shale and sandstone under present conditions. The results suggest that tritium has migrated only 110 m from the working point between 1967 and 2014. Although tritium is able to exchange between the gas and aqueous phases, the faster-diffusing gas phase is responsible for most of the tritium transport from the chimney. A hypothetical producing gas well located 340 m from the working point was added to the model to determine if tritiated water vapor (HTO) could migrate toward the well; results show that, because the low gas velocities could not compete with the high rate of radioactive decay, tritium would not reach the well. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗