In-Situ Measurements of Mechanical Properties Using Novel Automated Ball Indentation System

This paper presents the ABI® system in the context of nuclear power plant life extension and thermal annealing programs — two of the most economically significant applications in the nuclear industry. Published in ASTM STP 1204, the volume specifically addressed small specimen test techniques for reactor vessel thermal annealing and plant life extension.

The economic argument is straightforward: nuclear power plant license renewal from 40 to 60 years (and now to 80 years) requires demonstration that reactor vessel materials retain adequate fracture toughness despite decades of neutron irradiation. Conventional demonstration requires destructive testing of surveillance capsule specimens — irreplaceable material that is consumed with each test.

Haggag demonstrates that in-situ ABI® measurements on reactor vessel surveillance materials can substitute for destructive specimen removal, directly supporting the economic case for nuclear license renewal by conserving limited surveillance material for future use. The paper presents validation data showing agreement between ABI-derived properties and conventional test results on surveillance program materials.

Notably, Haggag served as co-editor of this ASTM STP volume along with W.R. Corwin and W.L. Server — two of the most prominent figures in nuclear pressure vessel technology. This editorial role reflected Haggag's growing stature in the reactor materials community and positioned ABI® as a central technology in the nuclear plant life extension discussion.