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Title page 1

Contents 5

ABSTRACT 4

ABBREVIATIONS AND ACRONYMS 9

1. INTRODUCTION 11

1.1. Background 12

1.1.1. Wet Storage Conditions 12

1.1.2. Normal Dry Storage Conditions 12

1.1.3. Transportation Conditions 13

1.2. Previous Reviews 13

1.2.1. OECD-NEA Report 14

1.2.2. OECD-NEA Report: FeCrAl Cladding 14

1.2.3. Review Article in Journal of Nuclear Material 15

1.2.4. EPRI Cr-Coated Cladding 15

1.2.5. EPRI ATF Report 16

2. OVERVIEW OF ATF CLADDING CONCEPT DEVELOPMENT 17

2.1. Westinghouse 17

2.2. Framatome 18

2.3. Global Nuclear Fuels 19

2.4. Japan 20

2.5. China 20

2.6. South Korea 20

2.7. Oak Ridge National Laboratory 21

2.8. Idaho National Laboratory 21

3. OVERVIEW OF CR-COATED ZR-ALLOY CLADDING 22

3.1. Overview of Cr Coating Techniques 24

3.1.1. Cold Spray 24

3.1.2. Physical Vapor Deposition 24

3.2. The Cr-Zr Phase Diagram 26

3.3. Eutectics 27

3.4. Brittle Phases 28

3.5. Cr-Coated Zr-Alloy Cladding Degradation and Failure Modes 28

4. OVERVIEW OF GNF FECRAL ALLOYS 30

4.1. FeCrAl Design 30

4.2. C26M 32

4.3. Kanthal® APMT 32

4.4. MA956 33

4.5. Possible Eutectics 33

4.6. FeCrAl Cladding Degradation and Failure Modes 34

5. STORAGE AND TRANSPORTATION OF SPENT NUCLEAR FUEL 36

5.1. Wet Storage of Spent Nuclear Fuel 37

5.1.1. Current Regulatory Framework 37

5.1.2. Application to Cr-Coated Zr-Alloy Cladding 38

5.1.3. Application to FeCrAl Cladding 39

5.2. Dry Storage of Spent Nuclear Fuel 40

5.2.1. Current Regulatory Framework 40

5.2.2. Application to Cr-Coated Zr-Alloy Cladding 43

5.2.3. Application to FeCrAl Cladding 44

5.2.4. Application to Fuels with High Burnup and Enhanced Enrichment 45

5.3. Transportation of Spent Nuclear Fuel 47

5.3.1. Current Regulatory Framework 47

5.3.2. Application to Cr-Coated Zr-Alloy Cladding 49

5.3.3. Application to FeCrAl Cladding 50

5.3.4. Application to Fuels with High Burnup and Enhanced Enrichment 51

5.4. Data Recommendation for Safety Evaluations 52

6. AVAILABLE DATA 55

6.1. Cr-Coated Zr-Alloy Cladding 55

6.1.1. Cladding Mechanical Properties 55

6.1.2. Cladding Fatigue 56

6.2. FeCrAl Cladding 56

6.2.1. Cladding Mechanical Properties 56

6.2.2. Cladding Thermal Properties 59

6.2.3. Cladding Fatigue 62

7. CONCLUSIONS 64

8. REFERENCES 66

APPENDIX A. PHENOMENA IDENTIFICATION AND RANKING TABLE (PIRT) FOR FUEL AND CLADDING PROPERTY CHANGES RELEVANT TO... 74

Tables 8

Table 3-1. Comparison of Cr-Coated Concepts Being Pursued by U.S. Nuclear Fuel Vendors 22

Table 4-1. Compositions (by Weight Percent) of C26m, Kanthal® Apmt, and Ma956 FeCrAl Alloys 30

Table 5-1. Comparison of Dose from High Burnup Fuel Assembly with Zircaloy and FeCrAl Cladding 40

Table 5-2. Fractions of Radioactive Materials Available for Release from High Burnup (up to 62 (GWd/MTU) SNF Under Conditions of Dry... 46

Table 5-3. Fractions of Radioactive Materials Available for Release from High Burnup (up to 62 GWd/MTU) SNF Under Conditions of Transport... 52

Table 5-4. Assessment Data that Could be Used to Justify the Safety Evaluation of a DSS and SNF Transportation Package Containing Fuel... 53

Table 6-1. Summary of Unirradiated Mechanical Properties Data for Cr-Coated Zr-Alloy Cladding 55

Table 6-2. Summary of Unirradiated Fatigue Data for Cr-Coated Zr-Alloy Cladding 56

Table 6-3. Summary of Mechanical Property Testing for Irradiated FeCrAl Cladding 57

Table 6-4. Summary of Unirradiated Thermal Property Testing for FeCrAl Cladding 59

Table 6-5. Summary of Fatigue Data for Unirradiated FeCrAl Cladding 62

Figures 7

Figure 3-1. Zr-Cr Phase Diagram (Arias and Abriata 1986) 27

Figure 4-1. FeCr Binary Alloy Phase Diagram Showing Phase Boundaries of α-Fe, α'-Cr, and σ-FeCr the Effect of a 4 w/o Al Addition on the... 31

Figure 4-2. Impact of Chromium and Aluminum Concentration in FeCrAl Alloys (Yamamoto, Field et al. 2020) 32

Figure 5-1. Overview of Safety Evaluation of a DSS (Taken from NUREG-2215) 42

Figure 5-2. Overview of Safety Evaluation of SNF Transportation (Taken from NUREG 2216) 48

Figure 6-1. Elastic Modulus of Zr-Based Alloys (Geelhood et al. 2020) and Various FeCrAl Alloys (Field 2018; Kanthal 2019; Special Metals 2004) 58

Figure 6-2. Unirradiated Yield Stress for Zr-Based Alloys (Geelhood et al. 2020) and Various FeCrAl Alloys (Field 2018; Special Metals Corporation... 59

Figure 6-3. Irradiated Yield Stress for Kanthal® APMT at 320 °C (Field et al. 2017) 59

Figure 6-4. Thermal Conductivity of Zr-Based Alloys (Geelhood et al. 2020) and Various FeCrAl Alloys (Field 2018; Special Metals 2004) 60

Figure 6-5. Thermal Expansion of Zr-Based Alloys (Geelhood et al. 2020) and Various FeCrAl Alloys (Field 2018; Yamamoto et al. 2019; Special Metals 2004) 61

Figure 6-6. Specific Heat of Zr-Based Alloys (Geelhood et al. 2020) and Various FeCrAl Alloys (Field 2018; Yamamoto et al. 2019; Special Metals 2004) 62

Figure 6-7. Fatigue Lifetime Curve for Unirradiated Zircaloy and Fatigue Data from FeCrAl (Fe-23.85 Cr-3.89Al) 63

Appendix Tables 8

Table A-1. Cr-Coated Zr-Alloy Cladding Property Changes that Could Impact Spent Fuel Storage and Transportation Analyses 79

Table A-2. FeCrAl Cladding Property Changes that Could Impact Spent Fuel Storage and Transportation Analyses 80

Table A-3. High Enrichment Fuel Property Changes that Could Impact Spent Fuel Storage and Transportation Analyses 81

Table A-4. High Burnup Fuel And Cladding Property Changes that Could Impact Spent Fuel Storage and Transportation Analyses 81

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