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
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
L. B. Freeman, B. R. Beaudoin, R. A. Frederickson, G. L. Hartfield, H. C. Hecker, S. Milani, W. K. Sarber, W. C. Schick
Nuclear Science and Engineering | Volume 102 | Number 4 | August 1989 | Pages 341-364
Technical Paper | doi.org/10.13182/NSE89-A23647
Articles are hosted by Taylor and Francis Online.
The light water breeder reactor (LWBR) operated at the Shippingport Atomic Power Station from 1977 to 1982, serving the electric power grid for the Greater Pittsburgh area. The LWBR was a pressurized water reactor (PWR) with several unique features: It was designed and proved to be a breeder with an end-of-life fissile fuel content ∼1.3% greater than beginning of life; the reactor used the 233U-Th fuel system; and it had a large Doppler coefficient, low reactivity worth of transient xenon, and a significant reactivity effect from transient 233Pa. There were no control rods or soluble poison, and reactivity was controlled by movable fuel. Core operations went extremely well. The design lifetime of 18 000 effective full-power hours was exceeded by 60% by utilizing a gradual reduction in power level. The overall capacity factor was 65%. Physics experiments showed good agreement with predictions of movable fuel reactivity worth, most temperature coefficients, breeding, power distribution, and xenon stability. Unexpected results occurred in measurements of flow coefficient of reactivity, zero power temperature coefficients early in life, and bred fissile fuel distribution. The LWBR technology has demonstrated that water-cooled breeder reactors can operate in existing water power plants much like conventional PWRs.