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Measurement of Neutron Production Doubledifferential Cross-sections on Carbon Bombarded with 430 MeV/Nucleon Carbon Ions

첫 페이지 보기
  • 발행기관
    대한방사선방어학회 바로가기
  • 간행물
    방사선방어학회지 KCI 등재 바로가기
  • 통권
    VOLUME 41 NUMBER 4 (2016.12)바로가기
  • 페이지
    pp.344-349
  • 저자
    Yutaro Itashiki, Youichi Imahayashi, Nobuhiro Shigyo, Yusuke Uozumi, Daiki Satoh, Tsuyoshi Kajimoto, Toshiya Sanami, Yusuke Koba, Naruhiro Matsufuji
  • 언어
    한국어(KOR)
  • URL
    https://www.earticle.net/Article/A290608

원문정보

초록

영어
Background: Carbon ion therapy has achieved satisfactory results. However, patients have a risk to get a secondary cancer. In order to estimate the risk, it is essential to understand particle transportation and nuclear reactions in the patient’s body. The particle transport Monte Carlo simulation code is a useful tool to understand them. Since the code validation for heavy ion incident reactions is not enough, the experimental data of the elementary reaction processes are needed. Materials and Methods: We measured neutron production double-differential cross-sections (DDXs) on a carbon bombarded with 430 MeV/nucleon carbon beam at PH2 beam line of HIMAC facility in NIRS. Neutrons produced in the target were measured with NE213 liquid organic scintillators located at six angles of 15, 30, 45, 60, 75, and 90°. Results and Discussion: Neutron production double-differential cross-sections for carbon bombarded with 430 MeV/nucleon carbon ions were measured by the time-of-flight method with NE213 liquid organic scintillators at six angles of 15, 30, 45, 60, 75, and 90°. The cross sections were obtained from 1 MeV to several hundred MeV. The experimental data were compared with calculated results obtained by Monte Carlo simulation codes PHITS, Geant4, and FLUKA. Conclusion: PHITS was able to reproduce neutron production for elementary processes of carbon-carbon reaction precisely the best of three codes.

목차

ABSTRACT
 Introduction
 Materials and Methods
  1. Experiment
  2. Analysis
  3. Simulation
 Results and Discussion
 Conclusion
 References

키워드

Carbon ion therapy Neutron DDX PHITS Geant4 FLUKA

저자

  • Yutaro Itashiki [ Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japan ] Corresponding author
  • Youichi Imahayashi [ Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japan ]
  • Nobuhiro Shigyo [ Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japan ]
  • Yusuke Uozumi [ Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japan ]
  • Daiki Satoh [ Nuclear Science and Engineering Center, Japan, Atomic Energy Agency, Ibaraki, Japan ]
  • Tsuyoshi Kajimoto [ Division of Energy and Environmental Engineering, Hiroshima University, Hiroshima, Japan ]
  • Toshiya Sanami [ Radiation Science Center, High Energy Accelerator Research Organization, Ibaraki, Japan ]
  • Yusuke Koba [ National Institute of Radiological Sciences, National Institutes for Quantum and Radiological Science and Technology, Chiba, Japan ]
  • Naruhiro Matsufuji [ National Institute of Radiological Sciences, National Institutes for Quantum and Radiological Science and Technology, Chiba, Japan ]

참고문헌

자료제공 : 네이버학술정보

간행물 정보

발행기관

  • 발행기관명
    대한방사선방어학회 [Korean Association For Radiation Protection]
  • 설립연도
    1975
  • 분야
    자연과학>기타자연과학
  • 소개
    회원 상호간의 협조와 친목을 도모함으로써 방사선방어에 관한 제반연구 및 발전에 이바지함을 물론 학술의 국제교류 및 국제학술단체와의 상호협력 증진에 기여함을 목적으로 하며, 이 목적을 달성하기 위하여 다음 각 호의 사업을 한다. 1. 방사선방어에 관한 학술연구발표회 및 강연회 등의 개최 2. 학회지 및 방사선방어에 관한 학술간행물의 발행 및 배포 3. 방사선방어에 관한 학술의 국제교류 및 협력 4. 방사선방어에 관한 국제학술자료의 조사, 수집 및 번역 5. 방사선방어에 관한 조사 및 연구용역 6. 회원의 연구활동을 위한 제반협조 7. 기타 본 학회의 목적 달성에 필요한 사항

간행물

  • 간행물명
    방사선방어학회지 [Journal of Radiation Protection and Research]
  • 간기
    계간
  • pISSN
    2508-1888
  • 수록기간
    1976~2026
  • 등재여부
    KCI 등재,SCOPUS
  • 십진분류
    KDC 559 DDC 629

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