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
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
August 2026
Nuclear Technology
July 2026
Fusion Science and Technology
Latest News
Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
Shigeaki Tsunoyama, Tohru Mitsutake, Shigeo Ebata, Shirley A. Sandoz
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 374-382
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33392
Articles are hosted by Taylor and Francis Online.
Applying an autoregressive (AR) technique to a boiling water reactor stability test yields two kinds of reactor stability performance indexes. One is characterized by the neutron flux to reactor pressure open-loop transfer function. The other is characterized by the closed-loop transfer function. Studies were performed on these reactor core stability indexes, using a one-dimensional transient model. To simulate these two kinds of stability characteristics in the time domain, the input/output relation for the system considered is important. In both cases, the output variable is the neutron flux. For the input state variable, in the case of the open-loop stability index, reactor pressure was chosen and adopted as a boundary variable to enable neglecting the feedback due to change in the reactor dome pressure. In the case of the closed-loop stability index, the vessel steam flow to the main steamline was adopted to separate the reactor response from the main steamline. Employing this procedure, both stability indexes were estimated by the one-dimensional reactor transient model. Comparing these indexes to those evaluated by the AR fitting and Fourier transform of small perturbation test data, it was concluded that the one-dimensional transient model predicts well the open- and closed-loop stability performance. Further, it was shown that the open-loop index conventionally used is a somewhat conservative one.