ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
May 2025
Nuclear Technology
Fusion Science and Technology
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.
George R. Fegan, Daniel I. Herborn, Steven M. Lippincott
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 13-18
Technical Paper | Reactor | doi.org/10.13182/NT78-A32086
Articles are hosted by Taylor and Francis Online.
Received January 31, 1977 Accepted for Publication September 7, 1977 The net free volume of the containment is an essential parameter in the loss-of-coolant accident (LOCA) containment pressure analysis for pressurized water reactors. For an optimized emergency core cooling system performance due to the importance of backpressure during the reflood phase of a LOCA, it is necessary to have the predicted pressure quite close to the design pressure. Using a geometric analysis, an estimate of 56 241.99 m3 (1 986 167 ft3) for the net free volume has been made for the containment of the Trojan nuclear plant. Two sets of data were produced from the normally scheduled structural integrity and integrated leak-rate tests on the Trojan containment. These data sets were used to arrive at two new estimates of the net free volume. A deterministic equation giving volume as a function of the slope of a linear relationship between depressurization and time was developed. After an analysis of the reliability of the data, estimates of this linear slope were made from the two data sets. These two slopes gave net free volume estimates of 58 000 m3 (2.05 × 106 ft3) and 57 650 m3 (2.036 × 106 ft3) when used in the deterministic equation. The maximum deviation from the geometric-based estimate was <4%.