MCNP 시뮬레이션을 통한 폴리에틸렌 코팅 탄화붕소 혼입 시멘트 페이스트의 중성자 차폐 성능 평가

Evaluation of Neutron Shielding Performance of Polyethylene Coated Boron Carbide-Incorporated Cement Paste using MCNP Simulation

  • 박재연 (한양대학교 건축공학과) ;
  • 지현석 (한양대학교 건축공학과) ;
  • 배성철 (한양대학교 건축공학과)
  • 발행 : 2018.11.16

초록

To develop an effective shielding material for spent fuel that emits fast neutrons is necessary. In this study, thermal neutron and fast neutron shielding performance of polyethylene coated boron carbide-incorporated cement paste was quantitatively analyzed by Monte Carlo N-Particle transport code (MCNP) simulations. As the results of the simulations, fast neutrons were effectively shielded through large quantity of hydrogen and boron elements in polyethylene and boron carbide.

키워드