Advanced searches left 3/3

Chromium - OSTI GOV

Summarized by Plex Scholar
Last Updated: 17 August 2022

* If you want to update the article please login/register

Semi-integral LOCA test of cold-spray chromium coated zircaloy-4 accident tolerant fuel cladding

. " Enhancing the mishap tolerance of PWRs came under significant factor to consider adhering to the 2011 Fukushima Daiichi nuclear reactor occasions. While the current nuclear gas are based on mature modern technology and have an exceptional operational record, more enhancing their strength through crash tolerant fuel r & d proceeds to be of passion. Specifically, the chromium covered dressed ATF innovation stands for a transformative change to improve the high temperature performance of existing Zircaloy claddings. Furthermore, despite several years of investigation of coated cladding, the important loss of coolant mishap performance of chromium layered cladding has had little attention. ".

Source link: https://www.osti.gov/biblio/1850475


Comparison of chromium poisoning between lanthanum strontium manganite and lanthanum strontium ferrite composite cathodes in solid oxide fuel cells

. " Degradation mechanisms of chromium poisoning have been extensively checked out for last 2 decades on various cathode materials for strong oxide fuel cells. While most researchers used half-cell experiments to check out the results of chromium impurities, this paper compares the deterioration sensations of LSM-YSZ and LSF-GDC cathodes in full cells under various operating conditions, specifically polarized current density and humidity over the cathode. In comparison, Cr deposition in LSF-based cell concentrates at the cathode surface under dry air condition, yet concentrates both at cathode surface and near electrolyte under humidified air condition. ".

Source link: https://www.osti.gov/biblio/1849126


Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties

. " In this paper we assess the distinctions in between previous transient important heat flux experiments making use of iron-chromium-aluminum, Inconel 600, and stainless-steel 316 alloy test sections and best-estimate modeling results from widely-used nuclear engineering systems and subchannel analysis tools. The thermal hydraulic efficiency and safety characteristics of FeCrAl are being examined to identify feasibility as a cladding material in Light Water Reactors. In this research, the results of the CHF experiments performed at air pressure and fixed inlet coolant temperature and mass change are compared to models integrated in the 5th version of the Reactor Excursion and Leak Analysis Program and CTF, the up-to-date variation of COBRA-TF created by the Consortium for Advanced Simulation of LWRs. We found that CHF depends most highly on the CHF multiplier and thermophysical properties. ".

Source link: https://www.osti.gov/biblio/1848158

* Please keep in mind that all text is summarized by machine, we do not bear any responsibility, and you should always check original source before taking any actions

* Please keep in mind that all text is summarized by machine, we do not bear any responsibility, and you should always check original source before taking any actions