Student: Bulička Jakub
Supervisor: Ing. Libor Juha, CSc. (FzÚ AV ČR)
Consultanting. Tomáš Burian, Ph.D. (FzÚ AV ČR), Doc. RNDr. Jan Wild, CSc.
Status: Assigned
Abstract:
Despite the recent advances achieved in the study of inertial confinement fusion (ICF) of light elements, numerous steps leading to an ICF reactor generating electricity for the grid are still subjected to extensive research. One of the most challenging problems is to ensure the long-term resistance of the reactor first (inner) walls. This thesis should deal with laboratory investigations of damage to various refractory materials (W,BN,SiC) induced by different fusion plasma emissions (both photons and charged particles) and debris liberated from targets (fuel capsules) exposed to intense laser radiation (direct drive ICF).
Literature:
1. T. Okazaki, Fusion Reactor Design: Plasma Physics, Fuel Cycle System, Operation and Maintenance, Wiley-VCH, NY-Weinheim 2022.
2. T. J. Tanaka, G. A. Rochau, R. R. Peterson, and C. L. Olson, “Testing IFE materials on Z”, J. Nucl. Mater. 347, 244–254 (2005).
3. M. Kaufmann and R. Neu, “Tungsten as first wall material in fusion devices”, Fusion Eng. Design 82, 521-527 (2007).
4. E. Lassner and W.-D. Schubert, Tungsten: Properties, Chemistry, and Technology of the Element, Alloys, and Chemical Compounds, Springer, New York 1999.
5. O. I. Buzhinskij, I. V. Opimach, A. V. Kabishev, V.V. Lopatin, and Y. P. Surov: “Application of pyrolytic boron nitride in fusion devices”, J. Nucl. Mater. 173, 179-184 (1990).