Decommissioning of nuclear power plants generates a large amount of radioactive waste in a short period. Moreover, Radioactive waste has various forms including a large volumes of metal, concrete, and solid waste. The disposal of decommissioning waste using 200 L drums is inefficient in terms of economics, work efficiency, and radiation safety. Therefore, The Korea Radioactive Waste Agency is developing large containers for the packaging, transportation, and disposal of decommissioning waste. Assessing disposability considering the characteristics of the radioactive waste and facility, convenience of operation, and safety of workers is necessary. In this study, the exposure dose rate of workers during the disposal of new containers was evaluated using Monte Carlo N-Particle Transport code. Six normal and four abnormal scenarios were derived for the assessment of the dose rate in a near surface disposal facility operation. The results showed that the calculated dose rates in all normal scenarios were lower than the direct exposure dose limitation of workers in the safety analysis report. In abnormal scenarios, the work hours with dose rates below 20 mSv·y−1 were calculated. The results of this study will be useful in establishing the optimal radiation work conditions.

1. Introduction
2. Characteristics of Packages
3. MCNP Modeling
4. Exposure Scenarios and Dose Limits
    4.1 Normal Scenarios
    4.2 Abnormal Scenarios
5. Results
6. Conclusions
REFERENCES

• Yeseul Cho(Korea Radioactive Waste Agency)
• Hoseog Dho(Korea Radioactive Waste Agency)
• Hyungoo Kang(Korea Radioactive Waste Agency)
• Chunhyung Cho(Korea Radioactive Waste Agency) Corresponding Author