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Division Spotlight
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.
Yassin A. Hassan, Sibashis S. Banerjee
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 191-206
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35030
Articles are hosted by Taylor and Francis Online.
A simulation of the loss of residual heat removal (RHR) system during midloop operations was performed using the RELAP5/MOD3 thermal-hydraulic code. The experiment was conducted at the Rig of Safety Assessment (ROSA)-IV/Large-Scale Test Facility. The experiment involved a 5% cold-leg break along with the loss of the RHR system. The transient was simulated for 3040 s. Core boiling and subsequent primary system pressurization occurred after the initiation of the transient. There was a good agreement between the measured and the calculated data until the loop seal clearing (LSC). It was found that the steam condensation was underpredicted in the calculations. This caused the calculated data after the LSC to differ from that of the measured data. The core rod surface temperature excursion around the occurrence of the LSC was not calculated. Overall, there was good qualitative agreement between the measured and the calculated data. The calculations, performed on the CRAY-YMP supercomputer, took over 60 h of CPU time for a transient of 51 min.