Earticle

초록

영어

Background: The installation and removal of nozzle dam work is one of the representative maintenance works in the steam generator primary side and can result in high levels of exposure due to the Chalk River unidentified deposit deposited inside the steam generator. Therefore, it is necessary to assess the radiation dose to workers installing and removing the nozzle dam to determine the exposure level for each task. This study assessed the radiation dose to workers installing and removing the nozzle dam during the overhaul period. Materials and Methods: The work scenarios for installation and removal of the nozzle dam were analyzed based on Advanced Power Reactor 1400 (APR1400) mock-up operation video and worker questionnaire. Then, based on the steam generator design data presented in the APR1400 design criteria document (DCD), the steam generator was simulated using Monte Carlo N-Particle (MCNP) code. Based on analyzed work scenarios and simulated steam generator, the radiation doses to workers were assessed. Results and Discussion: The work scenarios were analyzed for the four sub-works and the steam generator was simulated using MCNP6. The simulated steam generator was used to derive dose rates for each work location. For each sub-work, the assessment results of radiation doses were in the range of 2.13–4.51 man·mSv. For each worker, the radiation doses were in the range of 1.01–2.70 mSv. The highest radiation dose to workers was about 5.4% of the annual dose limit for workers (based on a maximum of 50 mSv per year). In this study, the source term was set using the specific activity of each radionuclide provided as conservative values in the APR1400 DCD. Consequently, the results of the dose assessment are likely to be somewhat conservative. Conclusion: The results of this study can be used for optimizing radiation exposure to workers installing and removing nozzle dam during the overhaul period.

목차

ABSTRACT
Introduction
Materials and Methods
1. Analysis of the Work Scenario
2. MCNP Simulation of a Steam Generator
3. Assessment of Radiation Dose
Results and Discussion
1. Results of Work Scenario Analysis
2. Results of Simulation for the Steam Generator
3. Results of Dose Assessment
Conclusion
Conflict of Interest
Acknowledgements
Ethical Statement
Author Contribution
References

키워드

저자

• [ Ji Woo Kim | Department of Nuclear Engineering, Kyung Hee University, Yongin, Republic of Korea ]
• Ju Young Kim [ Department of Nuclear Engineering, Kyung Hee University, Yongin, Republic of Korea ]
• Dae Ho Lee [ Department of Nuclear Engineering, Kyung Hee University, Yongin, Republic of Korea ]
• Kwang Pyo Kim [ Department of Nuclear Engineering, Kyung Hee University, Yongin, Republic of Korea ] Corresponding Author

참고문헌

발행기관

간행물

표지보기 관심저널 등록

• 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