Comparison of Physics Model for 600 MeV Protons and 290 MeV·n<sup>-1</sup> Oxygen Ions on Carbon in MCNPX

Lee, Arim; Kim, Donghyun; Jung, Nam-Suk; Oh, Joo-Hee; Oranj, Leila Mokhtari; Lee, Hee-Seock

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자료유형: 학술저널

저자정보: Lee, Arim (Pohang Accelerator Laboratory, POSTECH) Kim, Donghyun (Pohang Accelerator Laboratory, POSTECH) Jung, Nam-Suk (Pohang Accelerator Laboratory, POSTECH) Oh, Joo-Hee (Pohang Accelerator Laboratory, POSTECH) Oranj, Leila Mokhtari (Pohang University of Science and Technology) Lee, Hee-Seock (Pohang Accelerator Laboratory, POSTECH)

저널정보: 대한방사선방어학회 방사선방어학회지 방사선방어학회지 제41권 제2호

발행연도: 2016.1

수록면: 123 - 131 (9page)

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Background: With the increase in the number of particle accelerator facilities under either operation or construction, the accurate calculation using Monte Carlo codes become more important in the shielding design and radiation safety evaluation of accelerator facilities. Materials and Methods: The calculations with different physics models were applied in both of cases: using only physics model and using the mix and match method of MCNPX code. The issued conditions were the interactions of 600 MeV proton and $290MeV{\cdot}n^{-1}$ oxygen with a carbon target. Both of cross-section libraries, JENDL High Energy File 2007 (JENDL/HE-2007) and LA150, were tested in this calculation. In the case of oxygen ion interactions, the calculation results using LAQGSM physics model and JENDL/HE-2007 library were compared with D. Satoh's experimental data. Other Monte Carlo calculations using PHITS and FLUKA codes were also carried out for further benchmarking study. Results and Discussion: It was clearly found that the physics models, especially intra-nuclear cascade model, gave a great effect to determine proton-induced secondary neutron spectrum in MCNPX code. The variety of physics models related to heavy ion interactions did not make big difference on the secondary particle productions. Conclusion: The variations of secondary neutron spectra and particle transports depending on various physics models in MCNPX code were studied and the result of this study can be used for the shielding design and radiation safety evaluation.

#MCNPX #Physics model #Secondary neutron #Benchmarking

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