ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
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.