18.97.14.84
18.97.14.84
close menu
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 ( Park Jae-yeon ) , 지현석 ( Jee Hyeon-seok ) , 배성철 ( Bae Sung-chul )
UCI I410-ECN-0102-2019-500-001446160
This article is 4 pages or less.

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.

[자료제공 : 네이버학술정보]
×