Radiation Shielding Evaluation for Large Capacity CANDU Spent Fuel Transportation Cask

Jae-Hun Ko; Dong-Gyu Lee; In-Soo Jung

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Radiation Shielding Evaluation for Large Capacity CANDU Spent Fuel Transportation Cask

Jae-Hun Ko, Dong-Gyu Lee, In-Soo Jung

언어ENG
URLhttps://db.koreascholar.com/Article/Detail/389334

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)

2019 추계학술논문요약집 (2019.10)
pp.184-185

한국방사성폐기물학회 (Korean Radioactive Waste Society)

1. Introduction
2. Shielding Evaluation of IP-2 container
    2.1 Dose Rates Criteria
    2.2 Source Terms
    2.3 Analysis Model
    2.4 Shielding Evaluation
3. Shielding Evaluation Results
4. Conclusion
REFERENCES

저자

Jae-Hun Ko(Korea Nuclear Engineering & Service)
Dong-Gyu Lee(Korea Nuclear Engineering & Service)
In-Soo Jung(Korea Nuclear Engineering & Service)

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