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title page
Abstract
Contents
1. Introduction 9
1.1. Transport Package for Spent Nuclear Fuel 9
1.2. Objectives 11
2. CASTOR KN-12 12
2.1. CASTOR KN-12 12
2.2. Radiation Shielding of CASTOR KN-12 17
3. Source Term 18
3.1. ORIGEN-S and ORIGEN-ARP 18
3.2. Source Term Calculation 19
4. Monte carlo Simulation 20
4.1 MCNPX Code 20
4.2 Modeling of CASTOR KN-12 21
4.3 MCNPX setup 23
5. Results 31
5.1. Measured Result 31
5.2. Simulated Results 33
5.2.1. MCNPX simulation results for real spent fuel assemblies 33
5.2.2. Simulation results for several burn-up and cooling time 39
6. Discussion 51
요약문 (Summary) 53
References 55
감사의 글(Acknowledgement) 56
이력서(Curriculum Vitae) 58
Table 1. Input Parameters for Source Term Calculation 19
Table 2. Material Specification for the CASTOR KN-12 22
Table 3. Conversion Coefficients for the Ambient Dose Equivalent from Photon - the table A.21 of ICRP 74- 27
Table 4. Conversion Coefficients for the Ambient Dose Equivalent from Neutron - the table A.42 of ICRP 74- 28
Table 5. Measured Points 29
Table 6. Characteristics of Spent Nuclear Fuel Assemblies Used in the Radiation Shielding Performance Inspection 31
Table 7. Surface Radiation Dose Rate of CASTOR KN-12 - measured in February 2007, Kori Nuclear Power Plant. 32
Table 8. MCNPX Simulation Results for Real Nuclear Fuel Assemblies 35
Table 9. Surface Radiation Dose Rate for Photon (μSv/hr) 45
Table 10. Surface Radiation Dose Rate for Neutron (μSv/hr) 45
Table 11. Sum of Surface Radiation Dose Rate (μSv/hr) 46
Table 12. Minimum Cooling Time for Variant Burn-up 50
Figure 1. CASTOR KN-12 - General Arrangement Vertical Section 14
Figure 2. CASTOR KN-12 - General Arrangement Cross Section 15
Figure 3. CASTOR KN-12 - Basket Cross Section 16
Figure 4. CASTOR KN-12 Modeling - Basket Cross Section 24
Figure 5. CASTOR KN-12 Modeling - Basket Vertical Section 25
Figure 6. CASTOR KN-12 Modeling - 3D View with SABRINA 26
Figure 7. Measured Points 30
Figure 8. Source Term for Photon 34
Figure 9. Source Term for Neutron 34
Figure 10. Comparison Between Measured Data and Simulation Results (Photon) 37
Figure 11. Comparison Between Measured Data and Simulation Results (Neutron) 37
Figure 12. Radiation Dose Rates Simulated with 32,000 MWd/MTU, 17 Year Cooled 38
Figure 13. Photon Source Term - 32,000 MWd/MTU 40
Figure 14. Photon Source Term - 45,000 MWd/MTU 40
Figure 15. Photon Source Term - 58,000 MWd/MTU 41
Figure 16. Photon Source Terms Comparison for 7 year Cooled Fuels 41
Figure 17. Neutron Source Term - 32,000 MWd/MTU 42
Figure 18. Neutron Source Term - 45,000 MWd/MTU 42
Figure 19. Neutron Source Term - 58,000 MWd/MTU 43
Figure 20. Neutron Source Terms Comparison for 7 Year Cooled Fuels 43
Figure 21. Surface Dose Rates for Point No.1 - dose rate to burn-up 47
Figure 22. Surface Dose Rates for Point No.1 - dose rate to cooling time 47
Figure 23. Surface Dose Rates for Point No.8 - dose rate to burn-up 48
Figure 24. Surface Dose Rates for Point No.8 - dose rate to cooling time 48
Figure 25. Surface Dose Rates for Point No. 12 - dose rate to burn-up 49
Figure 26. Surface Dose Rates for Point No. 12 - dose rate to cooling time 49
Figure 27. Minimum Cooling Time for Variant Burn-up 50
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