Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “STEAM”

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.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 685 records · Page 38

Flexible Design for Steam Generation in an SMR Module

The intermediate heat exchanger is a key aspect of the JUMP tertiary loop. An IHX will be required as an interface between the main steam side and secondary side of the NuScale Power Module and coupled TES or energy users. This project examines the preliminary design of the IHX to establish a design range for detailed design and explore the relationships between variables.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

High temperature steam oxidation of Cr-coated SiCf/SiC composite for LWR cladding applications

Chromium-coated silicon carbide fiber-reinforced ceramic matrix composites are potentially applicable to accident tolerant fuel cladding in light water reactors. Cr-coated silicon carbide composite, chemical vapor deposited silicon carbide, and pure Cr-metal were oxidized in 100% steam at atmospheric pressure for 4 hours using a thermogravimetric analyzer. Post-oxidation chemical analysis, phase identification and microstructural characterization indicates that the Cr coating layers did not adversely affect silicon carbide substrate under these conditions.

Lee, Yoonjo↗

High temperature steam separation membrane

Ceramic proton-conducting oxide membranes are described herein, which are useful for separating steam from organic chemicals under process conditions. The membranes have a layered structure, with a dense film of the perovskite over a porous composite substrate comprising the perovskite material and a metallic material (e.g., Ni, Cu, or Pt). The perovskite comprises an ABO 3 -type structure, where “A” is Ba and “B” is a specified combination of Ce, Zr, and Y. The perovskite ceramic materials described herein have an empirical formula of Ba(Ce x Zr 1-x-n Y n )O 3-δ , wherein 0<x<0.8 (e.g., 0.1≤x≤0.7 or 0.2≤x≤0.5); and 0.05≤n≤0.2; and δ=n/2. In some embodiments n is about 0.2. In some other embodiments 0.6≤x≤0.8; and n is about 0.2, such as Ba(Ce 0.7 Zr 0.1 Y 0.2 )O 3-δ , also referred to herein as BCZY712.

Lee, Tae H.↗

Stability of refractory materials in high temperature steam

The present invention relates, in part, to a discovery of a method for using atomic layer deposition (ALD) to improve the stability of refractory materials in high temperature steam, and compositions produced by the method.

Weimer, Alan W.↗

IP-2 Steam Generator Lower Assembly Packaging, Transport and Disposal - 16510

WMG, Inc. led a team of industry experts in the first of its kind packaging, transportation and disposal of four (4) Steam Generator Lower Assemblies (SGLAs). The project had a number of significant challenges including qualifying the SGLAs as IP-2 packages, implementing roadway improvements and orchestrating the use of three different modes of transportation. In the end, these SGLAs would be the first large components disposed at the WCS Disposal facility in Andrews Texas. The client was re-purposing the SGLA storage mausoleum for 'Fukushima equipment' preparedness so it became necessary to dispose of the assemblies. The WMG team needed to: - Dismantle the mausoleum to allow removal of the SGLAs, - Design, fabricate, deliver and install IP-2 SGLA packaging, and - Transport the packaged SGLAs from the client to the WCS facility for disposal. After qualifying the packaging as IP-2 containers, the SGLAs were loaded onto special equipment for over-the-road transport to the harbor in Kewaunee, WI. Following trans-load, the SGLAs were barged down Lake Michigan through the Mississippi River to the Port of Houston for another trans-load. The SGLAs arrived by rail at WCS' Andrews TX facility. Each transport segment required coordination for transport clearances, proper marking, labeling and placarding for that particular mode of transport as well as coordination with the team involved in moving the large packages from one conveyance to another. The project was completed with zero safety issues, significantly below dose goals, ahead of schedule, and within budget. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Steam Corrosion Investigation of Single Silicon Carbide Nanostructures

Silicon carbide (SiC) has been advanced as an alternative to zircaloy for use as an accident-tolerant fuel cladding material in next-generation water-cooled reactors. This is due, in large part, to the predicted superior corrosion resistance of SiC, as compared to zircaloy, particularly at the high temperatures that are obtained in a nuclear reactor under accident conditions. The other favorable performance metrics of SiC include its enhanced mechanical stability, low neutron absorption, low chemical reactivity, and high radiation stability. Past reports, which include theoretical and isolated experimental activities, have studied the corrosion of bulk-scale SiC in reactor-like conditions. This report will present high-temperature steam corrosion results from single SiC nanofiber-based constructs. The changes in microstructure, and the evolution of oxide thickness and SiC recession with progressive corrosion will be characterized at the atomic-to-nanoscale using transmission electron microscopy (TEM). Furthermore, the corrosion-induced degradation in mechanical properties of the SiC nanofibers will be characterized using three-point bending tests involving an atomic-force microscope (AFM) in the contact mode.

36 MATERIALS SCIENCE↗

High Temperature Steam Electrolysis Process Model

The code models the operation of a high temperature steam electrolysis (HTSE) plant coupled with a nuclear power plant, and provides calculations of the process energy requirements; water feed stream flow rate requirements; process cooling requirements; process conditions such as temperature, pressure, and flow rate, throughout the process; product purity and flow rate, as well as data that can be used to determine the sizing, performance, and cost specifications of individual equipment components that comprise the system.

Wendt, DanielS (0000000344914296)↗

Effect of aluminum on the FeCr(Al) alloy oxidation resistance in steam environment at low temperature (400 °C) and high temperature (1200 °C)

The effect of aluminum in the FeCr(Al) alloys on the corrosion behavior was studied at two temperatures (400 °C and 1200 °C). For the Fe-21Cr alloy, Cr 2 O 3 layer was formed upon exposure to both temperatures. The addition of Al altered the corrosion mechanism of the alloy. At 1200 °C, a thin α-Al 2 O 3 is formed on the Fe-21Cr-5.5Al alloy. Whereas, at low temperature, a continuous Cr 2 O 3 is formed at the top with an internal Al 2 O 3 layer. These results show that FeCrAl alloys hold promise as Fuel Cladding Materials with Al playing a crucial role under operational as well as accident-like conditions.

36 MATERIALS SCIENCE↗