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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
Yukiharu Ohga
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 465-474
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Safety | doi.org/10.13182/NT83-A33171
Articles are hosted by Taylor and Francis Online.
A program analyzing long-term transients after abnormal incidents, excluding loss-of-coolant accidents, has been developed to assess emergency operation procedures for cold shutdown of reactors. The main program features are:1. The thermal hydraulics in both the reactor pressure vessel (RPV) and the primary containment vessel (PCV) are treated.2. Analytical models of the cooling system are included for not only the emergency core cooling system but other cooling systems that are effective for RPV and PCV cooling.3. The on /off switching of cooling systems by plant interlocks, component failures, and operator actions is simulated.The applicability of this program has been evaluated by simulation of long-term thermal-hydraulic behavior of the boiling water reactor transients initiated by loss of feedwater. From the evaluation results, it has been confirmed that the main program models can assess emergency operation procedures.