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Measurements of thermal neutron distribution of nuclear fuel using a plastic fiber-optic sensor

플라스틱 광섬유 센서를 이용한 핵 연료의 열중성자 분포도 측정

  • Jang, Kyoung-Won (School of Biomedical Engineering, Research Institute of Biomedical Engineering, Konkuk University) ;
  • Cho, Dong-Hyun (School of Biomedical Engineering, Research Institute of Biomedical Engineering, Konkuk University) ;
  • Yoo, Wook-Jae (School of Biomedical Engineering, Research Institute of Biomedical Engineering, Konkuk University) ;
  • Seo, Jeong-Ki (School of Biomedical Engineering, Research Institute of Biomedical Engineering, Konkuk University) ;
  • Heo, Ji-Yeon (School of Biomedical Engineering, Research Institute of Biomedical Engineering, Konkuk University) ;
  • Lee, Bong-Soo (School of Biomedical Engineering, Research Institute of Biomedical Engineering, Konkuk University) ;
  • Moon, Joo-Hyun (Department of Energy & Environmental System Engineering, Dongguk University) ;
  • Park, Byung-Gi (Department of Energy & Environmental Engineering, Soonchunhyang University) ;
  • Kim, Sin (Department of Nuclear & Energy Engineering, Applied Radiological Science Research Institute, Cheju National University) ;
  • Cho, Young-Ho (Department of Radiological Science, Catholic University)
  • 장경원 (건국대학교 의학공학부 의공학실용기술연구소) ;
  • 조동현 (건국대학교 의학공학부 의공학실용기술연구소) ;
  • 유욱재 (건국대학교 의학공학부 의공학실용기술연구소) ;
  • 서정기 (건국대학교 의학공학부 의공학실용기술연구소) ;
  • 허지연 (건국대학교 의학공학부 의공학실용기술연구소) ;
  • 이봉수 (건국대학교 의학공학부 의공학실용기술연구소) ;
  • 문주현 (동국대학교 에너지환경공학과) ;
  • 박병기 (순천향대학교 에너지환경공학과) ;
  • 김신 (제주대학교 에너지공학과) ;
  • 조영호 (대구가톨릭대학교 방사선과)
  • Published : 2009.09.30

Abstract

In this study, plastic optical fiber sensors which can measure thermal neutron dose in a mixed neutron-gamma field are developed and characterized. Using $^{252}Cf$ and $^{60}Co$ sources, the scintillators suitable for thermal neutron detection, are tested and the scintillating lights generated from a plastic optical fiber sensor in the Kyoto University Critical Assembly (kuca) core are measured. Also, the distributions of thermal neutron and gamma-ray are measured in a mixed field as a function of the distance from the center of the reactor core at KUCA and the distribution of thermal neutron is obtained using a subtraction method. Sensitivity of the fiber-optic radiation sensor system is about 0.49 V/mW according to power of the KUCA core and its relative error is about 1.2 %.

Keywords

References

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