Global ETD Search

Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.

Results

Showing 1 to 3 of 3 for “"FeCrAl alloy"”.

  1. Estimation of coping time in pressurized water reactors for accident tolerant fuel claddings

    … ATF claddings, monolayer iron-chromium-aluminum (FeCrAl) and Cr-coated Zircaloy, are experimentally investigated. Specifically, this work investigates the high-temperature oxidation characteristics of FeCrAl alloy after exposure to 1000-1400 °C steam for 1 hour. A model for oxidation of FeCrAl …

    mit Repository record for Estimation of coping time in pressurized water reactors for accident tolerant fuel claddings (opens in a new tab)

  2. Application of advanced fuel concepts for use in innovative pressurized water reactors

    … For an ATF cladding to replace zirconium alloys, it must be economically viable by having similar fuel cycle costs to today's materials. Four proposed materials are examined: stainless steel (SS), FeCrAl alloy, molybdenum (Mo) and SiC CMC, each having its own development time and costs. …

    mit Repository record for Application of advanced fuel concepts for use in innovative pressurized water reactors (opens in a new tab)

  3. BULK NANOSTRUCTURED STEELS FOR NUCLEAR REACTOR AND EXTREME ENVIRONMENT APPLICATIONS

    <p>"Candidate accident tolerant FeCrAl fuel (ATF) claddings for light water reactors (LWRs) need to be thinner than current Zircaloys owing to higher neutronic penalty, demanding an improvement in strength. Therefore, equal channel angular pressing (ECAP), and high-pressure torsion (HPT) were used …

    must-thes Repository record for BULK NANOSTRUCTURED STEELS FOR NUCLEAR REACTOR AND EXTREME ENVIRONMENT APPLICATIONS (opens in a new tab)