Page 1
Page 2
Page 3
Page 4
Page 5
Page 6
Page 7
Page 8
Page 9
Page 10
Page 11
Page 12
Page 13
Page 14
Page 15
Page 16
Page 17
Page 18
Page 19
Page 20
Page 21
Page 22
Page 23
Page 24
Page 25
Page 26
Page 27
Page 28
Page 29
Page 30
Page 31
Page 32
Page 33
Page 34
Page 35
Page 36
Page 37
Page 38
Page 39
Page 40
Page 41
Page 42
Page 43
Page 44
Page 45
Page 46
Page 47
Page 48
Page 49
Page 50
Page 51
Page 52
Page 53
Page 54
Page 55
Page 56
Page 57
Page 58
Page 59
Page 60
Page 61
Page 62
Page 63
Page 64
Page 65
Page 66
Page 67
Page 68
Page 69
Page 70
Page 71
Page 72
Page 73
Page 74
Page 75
Page 76
Page 77
Page 78
Page 79
Page 80
Page 81
Page 82
Page 83
Page 84
Page 85
Page 86
Page 87
Page 88
Page 89
Page 90
Page 91
Page 92
Page 93
Page 94
Page 95
Page 96
Page 97
Page 98
Page 99
Page 100
Page 101
Page 102
Page 103
Page 104
Page 105
Page 106
Page 107
Page 108
Page 109
Page 110
Page 111
Page 112
Page 113
Page 114
Page 115
Page 116
Page 117
Page 118
Page 119
Page 120
Page 121
Page 122
Page 123
Page 124
Page 125
Page 126
Page 127
Page 128
Page 129
Page 130
Page 131
Page 132
Page 133
Page 134
Page 135
Page 136
Page 137
Page 138
Page 139
Page 140
Page 141
Page 142
Page 143
Page 144
Page 145
Page 146
Page 147
Page 148
Page 149
Page 150
Page 151
Page 152
Nuclear Science User Facilities 136 Irradiation and Post-Irradiation Examination of Alloys X-750 and XM-19 Electric Power Research Institute Pilot Program Phase III Cooperative Research and Development Agreement No. 12-CR-06 John H. Jackson Idaho National Laboratory john.jacksoninl.gov As a means of establishing a basis for the development and execution of joint ATR NSUF industry programs the Electric Power Research Institute EPRI and ATR NSUF have developed a pilot program involving shared costs and responsi- bilities. In addition to providing data this EPRI pilot project is designed to Develop administrative protocols for the projects research such as cooperative agreements and funding. Develop portions of the research capa- bilities and staffing required to address future research and development needs. Develop a protocol for validating data with industry particularly stress cor- rosion crack SCC growth rate data. This project is important for three reasons first it is the initial industry pilot project for ATR NSUF and estab- lishes protocols for these types of proj- ects second it is a full cradle-to-grave characterization of reactor internal material including baseline character- ization irradiation and post-irradiation examination PIE third it is the first project to utilize two newly installed tools the controlled water chemistry Loop 2A in the ATR center flux trap and the irradiation-assisted stress corrosion crack IASCC test systems. Project Description Discussions between ATR NSUF and EPRI resulted in a decision to focus on investigation of the fracture toughness and IASCC growth rates of irradiated high-strength alloys used for boiling water reactor BWR repair hardware. Very little of this data exist for the nickel Ni-based alloy X-750 or for XM-19 a nitrogen N-strengthened austenitic stainless steel at the exposure levels of interest up to 1x1021 ncm2 . The focus of this EPRI pilot project is on irradiation and characterization of these alloys in both un-irradiated baseline and irradiated states and is being conducted in three phases. In Phase I researchers completed the fabrication of specimens from mate- rials provided by EPRI and established the baseline fracture toughness and crack growth rates CGR of un-irra- diated material. In Phase II they completed the design and fabrication of specimen holders and performed a safety analysis on a test train in order to meet EPRI objectives for irradiation of tensile and compact tension speci- mens utilizing Loop 2A in the center flux trap of ATR Figure 1. In the current and final Phase III researchers are performing irradiation and PIE of the EPRI specimens previously tested in their unirradiated state. This is the first project to utilize two newly-installed tools Loop 2A in the ATR center flux trap and the irradiation stress corrosion cracking IASCC test systems. Figure 1. Repair hardware of interest for this study.