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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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Nuclear Science and Engineering
April 2025
Nuclear Technology
Fusion Science and Technology
Latest News
MC&A and safety in advanced reactors in focus
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Go deeper: A recording of the full webinar “Updates on Advanced Nuclear Reactor Security and Material Control and Accounting,” which is available only to ANS members, can be viewed here.
Saerom Kwon, Satoshi Sato, Ryuta Kasada, Satoshi Konishi
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 599-603
Nuclear Systems: Analysis and Experiments | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST12-581
Articles are hosted by Taylor and Francis Online.
This study evaluates tritium production and breeding behavior in a LiPb blanket module with the neutron transport code MCNP using nuclear cross-section data from FENDL-2.1 libraries. The calculation results suggest that a sufficient tritium breeding ratio (TBR) can be obtained in the SiC-LiPb blanket concept and therefore a proper integral experiment on LiPb with DT neutrons can be planned for a small test module. Also, TBR, neutron shielding and nuclear heating in the module were evaluated. With the results of TBR and results from actual neutron generation devices, we have proposed a plan for an integral experiment with a measurable tritium amount.
