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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Ge-Ping Yu, Bau-Shei Pei, Ying-Pang Ma
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 147-159
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34237
Articles are hosted by Taylor and Francis Online.
A best-estimate transient analysis performed with the RETRAN-02 code is used to demonstrate that two reactor trip setpoints can be modified to improve plant operating margin and eliminate unnecessary reactor trips in the Maanshan three-loop Westinghouse pressurized water reactor. The trip setpoint relaxation analyses involve the steam generator water level and turbine trip. Analytical results show that for a loss-of-secondary-heat-sink event, the steam generator low-low-level reactor trip signal (SGLLRTS) setpoint can be adjusted down from 17 to 5% narrow-range water level span at low power level (<50%) without opening the primary-side power operated relief valves (PORVs). The effects of the automatic control rod on a loss-of-normalfeedwater transient are discussed. The reactor can be tripped by other signals if the SGLLRTS is inhibited at high power level. The turbine trip reactor trip signal setpoint can be lowered from 10 to 30% power. American National Standard design conditions and the prevention of pressurizer PORV opening to avoid a small loss-of-coolant accident are considered the safety criteria for the relaxation of trip setpoints.