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
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
X-energy raises $700M in latest funding round
Advanced reactor developer X-energy has announced that it has closed an oversubscribed Series D financing round of approximately $700 million. The funding proceeds are expected to be used to help continue the expansion of its supply chain and the commercial pipeline for its Xe-100 advanced small modular reactor and TRISO-X fuel, according the company.
Han Gyu Joo, Jae-Jun Jeong, Byung-Oh Cho, Won Jae Lee, Sung Quun Zee
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 166-179
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT142-166
Articles are hosted by Taylor and Francis Online.
The refined core thermal-hydraulics (T-H) nodalization feature of the MARS/MASTER code is used to generate a high-fidelity solution to the OECD main steam line break benchmark problem and to investigate the effects of core T-H nodalization. The MARS/MASTER coupling scheme is introduced first that enables efficient refined node core T-H calculations via the COBRA-III module. The base solution is generated using a fine T-H nodalization consisting of fuel assembly-sized radial nodes. Sensitivity studies are performed on core T-H nodalization to examine the impacts on core reactivity, power distribution, and transient behavior. The results indicate that the error in the peak local power can be very large (up to 25%) with a coarse T-H nodalization because of the inability to incorporate detailed thermal feedback. A demonstrative departure from nucleate boiling (DNB) calculation shows no occurrence of DNB in this problem.