지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.6
- 수록면
- 785 - 794 (10page)
이용수
초록· 키워드
오류제보하기
The Argonne National Laboratory of the United States and the Kharkov Institute of Physicsand Technology of the Ukraine have been collaborating on the design, development andconstruction of a neutron source facility at Kharkov Institute of Physics and Technologyutilizing an electron-accelerator-driven subcritical assembly. The electron beam power is100 kW using 100-MeV electrons. The facility was designed to perform basic and appliednuclear research, produce medical isotopes, and train nuclear specialists. Thebiological shield of the accelerator building was designed to reduce the biological dose to lessthan 5.0e-03 mSv/h during operation. The main source of the biological dose for the acceleratorbuilding is the photons and neutrons generated from different interactions of leakedelectrons from the electron gun and the accelerator sections with the surrounding componentsand materials. The Monte Carlo N-particle extended code (MCNPX) was used for theshielding calculations because of its capability to perform electron-, photon-, and neutroncoupledtransport simulations. The photon dose was tallied using the MCNPX calculation,starting with the leaked electrons. However, it is difficult to accurately tally the neutron dosedirectly from the leaked electrons. The neutron yield per electron from the interactions withthe surrounding components is very small, ~0.01 neutron for 100-MeV electron and evensmaller for lower-energy electrons. This causes difficulties for the Monte Carlo analyses andconsumes tremendous computation resources for tallying the neutron dose outside theshield boundary with an acceptable accuracy. To avoid these difficulties, the SOURCE andTALLYXuser subroutines ofMCNPXwere utilized for this study.The generated neutrons werebanked, together with all related parameters, for a subsequent MCNPX calculation to obtainthe neutron dose. The weight windows variance reduction technique was also utilized forboth neutron and photon dose calculations. Two shielding materials, heavy concrete andordinary concrete, were considered for the shield design. The main goal is to maintain thetotal dose outside the shield boundary less than 5.0e-03 mSv/h during operation. The shieldconfiguration and parameters of the accelerator building were determined and are presentedin this paper.
목차
등록된 정보가 없습니다.
참고문헌 (13)
참고문헌 신청
Y. Gohar / 2006 / Accelerator-driven sub-critical facility: conceptual design development / Nucl. Instr. Meth. Phys. Res. A 562:870~874
Denise B. Pelowitz / 2009 / MCNPX.2.7.B Extension / Los Alamos National Laboratory, LA-UR-09e04150
Y.O. Lee / 2003 / Shielding Aspect of High Current Proton Linear Accelerator (KOMAC) / Proceedings of the Korean Nuclear Society Autumn Meeting
Y. S. Min / 2010 / Shielding Design for the Target Room of the Proton Accelerator Research Center / Journal of the Korean Physical Society 56(61):1971~1980
S. Ohnishi / 2010 / Radiation shielding design for IFMIF/EVEDA accelerator vault / J. Plasma Fusion Res 9:190~192
Denise B. Pelowitz / 2009 / MCNPX.2.7.B Extension / Los Alamos National Laboratory, LA-UR-09e04150
Y.O. Lee / 2003 / Shielding Aspect of High Current Proton Linear Accelerator (KOMAC) / Proceedings of the Korean Nuclear Society Autumn Meeting
Y. S. Min / 2010 / Shielding Design for the Target Room of the Proton Accelerator Research Center / Journal of the Korean Physical Society 56(61):1971~1980
S. Ohnishi / 2010 / Radiation shielding design for IFMIF/EVEDA accelerator vault / J. Plasma Fusion Res 9:190~192
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility
Nuclear Engineering and Technology
2018 .01
-
An Assessment of the Secondary Neutron Dose in the Passive Scattering Proton Beam Facility of the National Cancer Center
Nuclear Engineering and Technology
2017 .06
-
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
Nuclear Engineering and Technology
2024 .09
-
Analysis of Dose Distribution According to the Initial Electron Beam of the Linear Accelerator: A Monte Carlo Study
방사선방어학회지
2018 .01
-
Reevaluation of Photon Activation Yields of <sup>11</sup>C, <sup>13</sup>N, and <sup>15</sup>O for the Estimation of Activity in Gas and Water Induced by the Operation of Electron Accelerators for Medical Use
방사선방어학회지
2016 .01
-
Occupational radiation exposure control analyses of 14?MeV neutron generator facility: A neutronic assessment for the biological and local shield design
Nuclear Engineering and Technology
2020 .08
-
A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
방사선방어학회지
2016 .01
-
The multigroup library processing method for coupled neutron and photon heating calculation of fast reactor
Nuclear Engineering and Technology
2024 .04
-
Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3
Nuclear Engineering and Technology
2024 .02
-
Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source
Nuclear Engineering and Technology
2017 .06
-
Development and application analysis of high-energy neutron radiation shielding materials from tungsten boron polyethylene
Nuclear Engineering and Technology
2024 .06
-
전자선 선형가속장치 사용시설 방사선차폐 평가
방사선산업학회지
2020 .01
-
Effect of Heat Treatment on Radiation Shielding Properties of Concretes
방사선방어학회지
2018 .01
-
Attenuation Curves of Neutrons from 400 to 550 Mev/u for Ca, Kr, Sn, and U ions in Concrete on a Graphite Target for the Design of Shielding for the RAON In-flight Fragment Facility in Korea
Nuclear Engineering and Technology
2019 .01
-
A feasibility study of the Iranian Sun mather type plasma focus source for neutron capture therapy using MCNP X2.6, Geant4 and FLUKA codes
Nuclear Engineering and Technology
2020 .01
-
EQUIVALENT DOSE FROM SECONDARY NEUTRONS AND SCATTER PHOTONS IN ADVANCE RADIATION THERAPY TECHNIQUES WITH 15 MV PHOTON BEAMS
방사선방어학회지
2015 .01
-
Thermal neutron albedo and flux for different geometries neutron guide
Nuclear Engineering and Technology
2019 .01
-
Optimization of Target, Moderator, and Collimator in the Accelerator-based Boron Neutron Capture Therapy System: A Monte Carlo Study
Nuclear Engineering and Technology
2021 .06
-
Monte Carlo shielding evaluation of a CSNS Multi-Physics instrument
Nuclear Engineering and Technology
2019 .01
-
Electrical characteristics and deep-level transient spectroscopy of a fast-neutron-irradiated 4H–SiC Schottky barrier diode
Nuclear Engineering and Technology
2023 .01
이 논문의 저자 정보
최근 본 자료
댓글(0)
0