Bill Corwin Email & Phone Number

Serving as Subject Matter Expert on Advanced Reactor Materials for the Advanced Reactor Technology Program within the U.S. Department of Energy’s Office of Nuclear Energy. Providing guidance on program planning and integration to develop and qualify materials for Generation IV advanced high-temperature nuclear reactors, liaison with U.S. Nuclear Regulatory Commission and Codes & Standards bodies, and coordination of international activities on structural nuclear materials.

Responsible for program direction and integration to develop and qualify materials for Generation IV advanced high-temperature nuclear reactors, liaison with U.S. Nuclear Regulatory Commission and Codes & Standards bodies, and coordination of international activities on structural nuclear materials for the U.S. Department of Energy’s Office of Nuclear Energy.

Developed and directed program to qualify materials for Generation IV advanced high-temperature and small modular nuclear reactors on behalf of the U.S. Department of Energy. Provided liaison with U.S. Nuclear Regulatory Commission to aid in establishing regulatory guidance for advanced reactors, including serving as visiting staff to the NRC's Office of Research. Participated with national Codes & Standards bodies to expand design rules and qualified materials for advanced reactors. Chaired the Gen IV International Forum’s Very High Temperature Reactor Materials Project Management Board providing representation and international partner coordination for the U.S. DOE.

Responsible for investigating diverse advanced materials needs and developing solutions for the U.S. Department of Defense, NASA, homeland security, and the intelligence community.

Responsible for planning and execution of NRC-sponsored HSST and HSSI programs to ensure the integrity of light-water reactor pressure vessels. Major emphases included the development and application of linear-elastic & elastic-plastic fracture technology, impact of weld overlay cladding, and the determination & prediction of the influence of irradiation exposure on pressure vessel steels.

Investigated effects of irradiation on fracture of structural materials for light-water-cooled & advanced reactor systems, as well as environmental effects on creep, fatigue, and fatigue crack propagation in materials for high-temperature reactor systems. Included serving as a Visiting Scientist to Kernforschungszentrum Karlsruhe, Germany, to provide technical liaison between the U.S. Nuclear Regulatory Commission and the HDR Safety Research Project in Karlsruhe.