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


Tunc G. , Sahin H. M. , Sahin S.

INTERNATIONAL JOURNAL OF ENERGY RESEARCH, cilt.42, ss.198-206, 2018 (SCI İndekslerine Giren Dergi) identifier identifier

  • Cilt numarası: 42 Konu: 1
  • Basım Tarihi: 2018
  • Doi Numarası: 10.1002/er.3782
  • Dergi Adı: INTERNATIONAL JOURNAL OF ENERGY RESEARCH
  • Sayfa Sayıları: ss.198-206

Özet

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/m(2) (10(14) 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.