On the looming 10th anniversary of the Fukushima disaster at the Daiichi Power Station in Japan, PNNL looks back at the science and solidarity it has shared with Fukushima and its nuclear cleanup effort.
Innovative technology combines continuous, remote, real-time testing and monitoring of byproduct gasses, paving the way for faster advanced reactor development and testing.
Magazine cover article—“Combating corrosion in the world’s nuclear reactors”—features PNNL research leaders Mark Nutt, Aaron Diaz, and Mychailo Toloczko.
An international team used PNNL microscopy to answer questions about how uranium dioxide—used in nuclear power plants—might behave in long-term storage.
Twelve energy-related technologies developed at PNNL have been selected for additional technology maturation funding to help move them from the laboratory and field tests to the marketplace.
Superman may be known as the "Man of Steel," but scientific superheroes at the Department of Energy's Pacific Northwest National Laboratory are developing a novel approach for manufacturing metals with superior strength.
A PNNL study that evaluated the use of friction stir technology on stainless steel has shown that the steel resists erosion more than three times that of its unprocessed counterpart.
PNNL is advancing scientific frontiers and addressing challenges in energy, the environment and national security. So, in no particular order, here are PNNL's top 10 research accomplishments of 2018
Steve Short, a nuclear engineer at Pacific Northwest National Laboratory, has been selected as a fellow of the National Society of Professional Engineers.
On October 22, the U.S. Nuclear Regulatory Commission (NRC)granted Tennessee Valley Authority's (TVA's) Watts Bar Nuclear Generating Station a 40-year operating license for its new Unit 2 reactor. This is the first nuclear reactor to be granted an operating license by the NRC in two decades.
Pressurized water nuclear reactors in the United States generate about 13 percent of U.S. electricity. Though efficient, these reactors face a unique challenge with stress corrosion cracking (SCC). This type of corrosion is one of the primary life-limiting degradation mechanisms of nickel-base alloy pressure boundary components, such as instrumentation and control rod nozzles, the welds that attach these nozzles to the reactor vessel, and welds that connect feedwater piping to the reactor vessel. As interest grows in a more sustainable and efficient fleet of nuclear reactors across the world, there is increasing interest in characterizing SCC initiation response.
