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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Po Hu, Paul P. H. Wilson
Nuclear Technology | Volume 172 | Number 2 | November 2010 | Pages 143-156
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT10-A10901
Articles are hosted by Taylor and Francis Online.
This paper studies the U.S. reference Supercritical Water Reactor (SCWR) design with the newly extended coupled codes PARCS/RELAP5. Steady-state, burnup, and loss-of-feedwater transients are simulated. A possible flow reversal in moderator channels is found in the simulations, and the impact of this reversal on power peaking and reactivity is observed. The transient results show that the assembly with the maximum cladding surface temperature (MCST) and the assembly with the maximum power are different and that the MCST is within the material limit under the current design.