Reactor Safety & Lifetime Extension

Continued safe availability of nuclear power is dependent on the materials performance of structures and components of the nuclear facility. The integrity evaluation of nuclear reactor pressure vessels (RPVs), through material property measurements, is a critical safety assessment. One method for structural integrity evaluation of RPVs is to monitor mechanical property changes of the materials susceptible to neutron radiation embrittlement by periodic destructive testing of surveillance specimens (Charpy impact, tensile specimens, and fracture toughness, if available). Lifetime extension programs and mitigation processes such as thermal annealing increase the need for additional surveillance specimens as well as require reconstitution of available test materials.

The in-situ SSM technology provides nondestructive determinations of key mechanical and fracture toughness properties (tensile, ductility, and static and dynamic fracture toughness) of RPV materials to monitor the structural integrity of RPVs subjected to neutron embrittlement. It can be used to verify and quantify the recovery of ductility and fracture toughness following thermal annealing.

1. Byun, T. S., et al. "A Theoretical Model for Determination of Fracture Toughness of Reactor Pressure Vessel Steels in the Transition Region from Automated Ball Indentation Test," Journal of Nuclear Materials 252, 1998 pp. 187-194. (303k)

2. "Byun, T. S., et al. "Measurement of Through-the-Thickness Variations of Mechanical Properties in SA508 Gr.3 Pressure Vessel Steels Using Ball Indentation Test Technique," International Journal of Pressure Vessels and Piping Vol. 74, 1997 pp. 231-238.

3. "In-Situ Nondestructive Measurements of Key Mechanical Properties of Pressure Vessels Using Innovative Stress-Strain Microprobe (SSM) Technology," Final report No. DOE/ER/82115-1, Award no. DE-FG02-96ER82115, 1997. (1.63 MB)

4. "Nondestructive and Localized Measurements of Stress-Strain Curves and Fracture Toughness of Ferritic Steels at Various Temperatures Using Innovative Stress-Strain Microprobe™ Technology." Final report No. DOE/ER/82115-2, Award No. DE-FG02-96ER82115, 1999. (1.5 MB)

5. "Use of Portable/In Situ Stress-Strain Microprobe System to Measure Stress-Strain Behavior and Damage in Metallic Materials and Structures," ASTM STP 1318, 1997, pp 85-98. (199k)

6. "Effects of Irradiation Temperature on Embrittlement of Nuclear Pressure Vessel Steels," Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175, A. S. Kumar, D. S. Gelles, R. K. Nanstad, and E. A. Little, Eds., Philadelphia, 1993, pp. 172-185.