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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jul 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
September 2026
Nuclear Technology
August 2026
Fusion Science and Technology
Latest News
The human factor in licensing and operating the next generation of nuclear plants
As human factors specialists working at the intersection of human performance and nuclear operations, we are witnessing one of the nuclear sector’s most significant transitions in decades. The emergence of small modular reactors, microreactors, and other advanced designs is reshaping the industry’s landscape. Digital instrumentation and controls, passive safety systems, and increased automation are creating opportunities for greater safety margins and more flexible operation. These same features also fundamentally redefine what it means to “operate” a nuclear plant. Interactions among human roles, automation, and passive systems shape how people maintain awareness, exercise judgment, and intervene when necessary. These developments affect both operational realities and the regulatory foundations on which nuclear safety is built.
Tomohiko Tamaki, Masanori Ohtani, Yasuharu Kawabe
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 216-224
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3026
Articles are hosted by Taylor and Francis Online.
A steam generator tube rupture (SGTR) incident occurred in Mihama Unit 2 on February 9, 1991. This is the first SGTR incident where the emergency core cooling system was actuated in Japan. With some measures being taken to improve the model, the precise simulation of the SGTR using RETRAN-02/MOD4 was conducted. A nonequilibrium model was applied to the secondary side of the damaged SG to obtain a reasonable response of the secondary pressure. The model of the reactor upper head was improved to simulate void generation during reactor coolant system depressurization, and there was good agreement with the actual plant data.