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
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Chang Joon Jeong, Ho Chun Suk
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 215-223
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3729
Articles are hosted by Taylor and Francis Online.
The power pulse characteristics following a large loss-of-coolant accident have been analyzed for a Canada deuterium uranium (CANDU)-6 reactor core fueled with a CANDU flexible fueling recovered uranium fuel. The coupled simulations for the reactor physics and channel thermal-hydraulics phenomena are done using the RFSP and CATHENA codes. The 55% pump suction, 35% reactor inlet header, and 100% reactor outlet header breaks were selected. From the analysis results, it is known that the shutoff rods have enough reactivity for a reactor shutdown and to maintain it at a subcriticality state. Even with the highest power pulse, which occurred in a 100% reactor outlet header break, the fuel temperature was maintained below the fuel melting temperature. The summation of the initial stored energy and the transient pulse energy of the hottest fuel pin has a minimum 17% margin for the fuel breakup.