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.
Explore membership for yourself or for your organization.
Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
October 2025
Fusion Science and Technology
Latest News
The journey of the U.S. fuel cycle
Craig Piercycpiercy@ans.org
While most big journeys begin with a clear objective, they rarely start with an exact knowledge of the route. When commissioning the Lewis and Clark expedition in 1803, President Thomas Jefferson didn’t provide specific “turn right at the big mountain” directions to the Corps of Discovery. He gave goal-oriented instructions: explore the Missouri River, find its source, search for a transcontinental water route to the Pacific, and build scientific and cultural knowledge along the way.
Jefferson left it up to Lewis and Clark to turn his broad, geopolitically motivated guidance into gritty reality.
Similarly, U.S. nuclear policy has begun a journey toward closing the U.S. nuclear fuel cycle. There is a clear signal of support for recycling from the Trump administration, along with growing bipartisan excitement in Congress. Yet the precise path remains unclear.
Jae-Hyuk Eoh, Seyun Kim, Sang-Ji Kim, Seong-O Kim
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 216-232
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3894
Articles are hosted by Taylor and Francis Online.
The KLFR is a pool-type lead-cooled fast reactor, which has a core thermal output of 900 MW(thermal), and a reactor vessel auxiliary cooling system (RVACS) is employed to secure reliable decay heat removal (DHR) during the worst anticipated design-basis condition. Since the RVACS design is based on reliable and economic considerations, a sufficiently large DHR capacity and compact reactor vessel size are desirable. However, these two requirements compete with each other because a sufficient DHR capacity can be achieved by a larger vessel size with a consequential heavy lead coolant weight. An advanced RVACS concept that has a larger capacity with a more compact vessel size was developed. To increase the DHR capacity of the KLFR, which uses natural-air circulation cooling, the feasibility of heat transfer enhancement by introducing new design concepts to essentially reduce the heat transfer resistance of the radial heat transfer elements was investigated. As a result of this work, the parametric analysis results showed that the passive DHR capacity of the KLFR can be substantially increased by up to 24% when compared with the classical RVACS concept, and this feature makes a compact reactor vessel very feasible. With the proposed advanced RVACS concept, one could expect that the heat removal capacity of an RVACS-type passive DHR system will be increased.