[논문]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

Lee, Eunjoong; Kim, Junhyeok; Kim, Giyoon; Kim, Jinhwan; Park, Kyeongjin; Cho, Gyuseong

doi:10.1016/j.net.2018.09.005

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 원문보기

Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.51 no.1, 2019년, pp.275 - 283

Lee, Eunjoong (Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) , Kim, Junhyeok (Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) , Kim, Giyoon (Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) , Kim, Jinhwan (Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) , Park, Kyeongjin (Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) , Cho, Gyuseong (Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology)

Abstract ▼ AI-Helper

Rare isotope beam facilities require shielding data in early stage of their design. There is much less shielding data on neutrons from the reactions between heavy ion beams and matter than the data on neutrons produced by protons. The purpose of the present work is to produce and thus increase the amount of shielding data on neutrons generated by high-energy heavy ion beams based on the RAON in-flight fragment facility. Calculations were performed with the computational Monte Carlo codes PHITS and MCNPX. The secondary neutron source terms were evaluated at 550 MeV/u for Ca, Kr, and Sn and at 400 MeV/u for U ions on a graphite target. Source terms and attenuation lengths were obtained by fitting the ambient dose equivalent inside an ordinary concrete shield.

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가설 설정

The difference may have been caused by several factors. First, the chemical compositions and density levels of the concrete types differed. The shield of the reference consisted of TSF-5.

제안 방법

Geometry splitting and the Russian roulette methods were used as variancereduction techniques to ensure the accuracy of the simulations. The attenuation curves were fitted by three types of functions: a classical two-parameter formula, a double-exponential function, and a double-exponential function with three free parameters.

대상 데이터

Several types of ions have been considered due to the high dependency of the neutron production reaction on the mass of the primary ions. Among the various primary beams from O-16 to U-238 planned to be used in the RAON facility, four types of beams, Ca-48, Kr-86, Sn-112, and U-238, were selected as primary beams after considering mass distribution of the ions. In the RAON IF facility, each beam is accelerated to 550 MeV/u for Ca-48, Kr-86, and Sn-112 and to 400 MeV/u for U-238 with a beam power of 400 kW.
A point neutron source was centered inside the concrete shield. The concrete shield was modeled as a spherical shell with a thickness of 10 m. The inner radius of the shield was set to 90 m, which is sufficient to avoid the effects from the curvature of the wall.
Secondary radiation such as neutrons and gamma rays generated by the interaction between heavy ion beams and a target are attenuated by a shielding material. The purpose of this work is to produce extended shielding data of neutrons generated by highenergy heavy ion beams (550 Mev/u for calcium, krypton, and stannum, and 400 MeV/u for uranium) based on RAON IF facility. The shielding data is used as useful information for the design of the shield or dose estimation in the early stage of the facility design.

이론/모형

The conversion coefficient for the ambient dose equivalent was taken from ICRP-74 [17]. Geometry splitting and the Russian roulette methods were used as variancereduction techniques to ensure the accuracy of the simulations. The attenuation curves were fitted by three types of functions: a classical two-parameter formula, a double-exponential function, and a double-exponential function with three free parameters.
Neutron attenuation by a concrete shield and the ambient dose equivalent were computed using the MCNPX code. The source terms and the attenuation lengths were estimated using the simulation result.
The neutron source terms produced from the heavy ions were evaluated by the PHITS code. The attenuation of neutrons inside the concrete shield was estimated using the MCNPX code. Ambient dose equivalent and attenuation curves were fitted with the models.
The composition of the concrete matched that of ANSI/ANS ordinary concrete [16]. The conversion coefficient for the ambient dose equivalent was taken from ICRP-74 [17]. Geometry splitting and the Russian roulette methods were used as variancereduction techniques to ensure the accuracy of the simulations.
These spectra were used as a neutron source for the production of shielding data. The estimated neutron beams were transported in a spherical shielding geometry made of concrete using the MCNPX 2.7.0 code. The ambient dose equivalent according to the depths in the shield was obtained from the neutron transport information in the shield.
The shielding data is generally estimated with simple line-of-sight models. The neutron source terms produced from the heavy ions were evaluated by the PHITS code. The attenuation of neutrons inside the concrete shield was estimated using the MCNPX code.
The neutron yield and energy distribution up to 90º generated from heavy ions with energy levels from 400 to 590 MeV/u using a graphite target were calculated using the PHITS code.

참고문헌 (18)

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상세보기
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상세보기
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상세보기
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상세보기
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상세보기
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상세보기
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상세보기
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DOI : 10.1016/j.net.2018.09.005 [무료]
한국원자력학회 : 저널
Korea Open Access Journals : 저널
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