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Technical Paper

Demonstration of the Effectiveness of Monte Carlo-Based Data Sets with the Simplified Approach for Shielding Design of a Laboratory with the Therapeutic Level Proton Beam

원문정보

Bo-Lun Lai, Szu-Li Chang, Rong-Jiun Sheu

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초록

영어

Background: There are several proton therapy facilities in operation or planned in Taiwan, and these facilities are anticipated to not only treat cancer but also provide beam services to the industry or academia. The simplified approach based on the Monte Carlo-based data sets (source terms and attenuation lengths) with the point-source line-of-sight approximation is friendly in the design stage of the proton therapy facilities because it is intuitive and easy to use. The purpose of this study is to expand the Monte Carlo-based data sets to allow the simplified approach to cover the application of proton beams more widely. Materials and Methods: In this work, the MCNP6 Monte Carlo code was used in three simulations to achieve the purpose, including the neutron yield calculation, Monte Carlo-based data sets generation, and dose assessment in simple cases to demonstrate the effectiveness of the generated data sets. Results and Discussion: The consistent comparison of the simplified approach and Monte Carlo simulation results show the effectiveness and advantage of applying the data set to a quick shielding design and conservative dose assessment for proton therapy facilities. Conclusion: This study has expanded the existing Monte Carlo-based data set to allow the simplified approach method to be used for dose assessment or shielding design for beam services in proton therapy facilities. It should be noted that the default model of the MCNP6 is no longer the Bertini model but the CEM (cascade-exciton model), therefore, the results of the simplified approach will be more conservative when it was used to do the double confirmation of the final shielding design.

목차

ABSTRACT
Introduction
Materials and Methods
1. Neutron Yield Calculation and Validation
2. Monte Carlo-based Data Sets Generation
3. Dose Assessment around the Laboratory
Results and Discussion
1. Database of Shielding Parameters
2. Characteristics of the Radiation Field
3. Comparison of a Simplified Approach and Monte Carlo Method in Dose Assessment of Simple Shielding Design Case
Conclusion
Conflict of Interest
Acknowledgements
Author Contribution
References

저자정보

  • Bo-Lun Lai Radiation Protection Association R.O.C., Hsinchu, Taiwan
  • Szu-Li Chang Radiation Protection Association R.O.C., Hsinchu, Taiwan; Institute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu, Taiwan
  • Rong-Jiun Sheu Institute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu, Taiwan; Department of Engineering and System Science, National Tsing Hua University, Hsinchu, Taiwan

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