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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.