ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)
Dr. Per Peterson is a Co-Founder & Chief Nuclear Officer of Kairos Power. Dr. Peterson also holds the William and Jean McCallum Floyd Chair in the Department of Nuclear Engineering at the University of California, Berkeley.
He is an expert in topics related to high-temperature fission energy systems, safety and security of nuclear materials, and waste management. As a member of the Evaluation Methodology Group, he participated in the development of the Gen IV Roadmap while serving as co-chair for the Proliferation Resistance and Physical Protection Working Group. His research has contributed to the development of the passive safety systems used in the General Electric ESBWR and Westinghouse AP1000 reactor designs. With Charles Forsberg and Paul Pickard, in 2003, he proposed the FHR concept of a molten-salt cooled, solid fueled reactor.
Dr. Peterson graduated from the University of Nevada at Reno with a B.S. in Mechanical Engineering. He holds an M.S. and Ph.D. in Mechanical Engineering from the University of California, Berkeley.
Last modified July 28, 2023, 2:17pm EDT
