Evaluation of the radiation damage parameters of ODS steel alloys in the first wall of deuterium-tritium fusion-fission (hybrid) reactors

Abstract

Summary One of the most important parameters in the design of the fusion‐fission hybrid reactor is the selection of the first wall material. Because the oxide dispersion‐strengthened (ODS) steel alloys have high temperature oxidation, high radiation resistance, good hardness, and corrosion resistance properties, they are thought first wall candidate materials for fusion and fission applications. The objective of this paper is to determine the best radiation damage parameters of various experimental and commercial ODS steels (namely, 12Y1, 12YWT, 1DS, IDK, Eurofer97, MA956, MA957, and PM 2000). Neutron spectrum and average neutron energy throughout blanket, displacement per atom, hydrogen and helium production, nuclear heating, and tritium breeding ratio were calculated by using Monte Carlo methods with Monte Carlo neutron‐photon transport code and nuclear libraries named as ENDF/B‐VI and CLAW‐IV. It is assumed that calculated reactor has been operated full power during a year and neutron wall load is 2.25 MW/m2 (1014 n/s). All investigated first wall materials should be replaced between 3.5 and 4 years. All investigated materials provide minimum required tritium breeding ratio value, and when considering all the calculations performed in this work, 1DS ODS steel is the most suitable first wall materials with respect to other investigated ODS steels.

Plasma Facing Material by Self-Interstitial Solid Solution Strengthening – Problem, Proposition, and a Solution

“…At T > 2000 K only micron-size holes on the surface are formed in the irradiated tungsten which is not fuzz but again is a damage and is undesirable. Materials specially to be used in first wall [12,17,28,85,119,[122][123][124][125][126][127][128][129][130][131][132][133], blanket [134][135][136][137][138][139][140][141][142][143]…”

Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

“…Tungsten is a well-known material leading in FW material candidates but facing high sputtering or critical issues. In a tokamak, the frst observed huge sputtering efect in plasma originated from tungsten limiter [13], but it is still favorable material for a long operation [14].…”

Ab Initio Modeling of Y and O Solute Atom Interaction in Small Clusters within the bcc Iron Lattice

“…Atomic tomography experiments confirmed the presence of yttrium and oxygen within the host iron matrix also in a form of solute atoms . It also has been demonstrated that ODS steels remain stable after being exposed to neutron radiation …”