Material Studies for Lead Bismuth Eutectic Cooled Nuclear Applications
Research output: Thesis › Doctoral Thesis
Standard
2016.
Research output: Thesis › Doctoral Thesis
Harvard
Author
Bibtex - Download
}
RIS (suitable for import to EndNote) - Download
TY - BOOK
T1 - Material Studies for Lead Bismuth Eutectic Cooled Nuclear Applications
AU - Hosemann, Peter Martin
N1 - no embargo
PY - 2016
Y1 - 2016
N2 - Lead Bismuth Eutectic (LBE) is a candidate coolant for various nuclear applications because of its superior neutronic, chemical, thermal, and physical properties. Using LBE in nuclear applications has been proven challenging since LBE is corrosive to most structural metals in addition to the radiation environment. In this work candidate structural materials for various components were investigated for their corrosion and irradiation properties. LBE corrosion experiments were performed in different loop systems and detailed post corrosion testing analysis were completed down to atomic scale. This analysis was used to formulate a qualitative model of the corrosion/oxidation mechanism. In addition, irradiation experiments were performed to investigate the effects of irradiation on the properties of the same materials. Small scale post irradiation analyses were performed to evaluate the changes in mechanical properties and structure due to irradiation. In the end the studies of corrosion and irradiation are combined in experiments and theory.
AB - Lead Bismuth Eutectic (LBE) is a candidate coolant for various nuclear applications because of its superior neutronic, chemical, thermal, and physical properties. Using LBE in nuclear applications has been proven challenging since LBE is corrosive to most structural metals in addition to the radiation environment. In this work candidate structural materials for various components were investigated for their corrosion and irradiation properties. LBE corrosion experiments were performed in different loop systems and detailed post corrosion testing analysis were completed down to atomic scale. This analysis was used to formulate a qualitative model of the corrosion/oxidation mechanism. In addition, irradiation experiments were performed to investigate the effects of irradiation on the properties of the same materials. Small scale post irradiation analyses were performed to evaluate the changes in mechanical properties and structure due to irradiation. In the end the studies of corrosion and irradiation are combined in experiments and theory.
KW - Blei Wismuth Eutektisch Strahlenschädigung Flüssigmetallkühlung Reaktorwerkstoffe
KW - lead bismuth eutectic radiation damage in materials liquid metal cooling liquid metal cooled nuclear reactors nuclear reactor materials
M3 - Doctoral Thesis
ER -