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Comparative Study of Dose Evaluation of Liquid Effluent in Nuclear Power Plants for Radiological Impact on the Environment Review KCI 등재 SCOPUS
- 언어ENG
- URLhttps://db.koreascholar.com/Article/Detail/432752
pp.45-54
Currently, off-site dose calculations for nuclear power plants are conducted using a computer program (K-DOSE 60). The program is developed based on the regulatory guidelines of the Korea Institute of Nuclear Safety (KINS), which is a domestic nuclear regulatory agency. In this study, a domestic application of the International Atomic Energy Agency (IAEA) TRS (Technical Reports Series)-472 methodology for 3H and 14C in liquid effluents was studied. The dose-evaluation methods adopted and the program configuration for dose evaluation are described based on 3H and 14C in the liquid-effluent-evaluation module of the computer program. The accuracy of the program is verified by comparing the program-calculated results with hand calculation values. Furthermore, a comparative evaluation with LADTAP II, which is a liquid-effluent-evaluation methodology developed by the U.S. NRC (Nuclear Regulatory Commission), is performed. The result confirms that the program-calculated results for the IAEA TRS-472 methodology are consistent with the hand calculation values. Meanwhile, the result of comparative evaluation with LADTAP II indicates different results depending on the methodology used.
2. Off-site Dose Calculation MethodCaused by Liquid Effluent
2.1 Exposure Age Groups
2.2 Ingestion Dose Conversion Factor
2.3 Dose Evaluation Methodology
2.4 Exposure Pathway of Liquid Effluent
3. Off-site Dose Calculation Program forLiquid Effluent
4. Verification of Off-site CalculationProgram for Liquid Effluent
5. Conclusion
Conflict of Interest
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