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
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
Yuji Ishiguro
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 121-126
Technical Note | Fuel Cycle | doi.org/10.13182/NT83-A33150
Articles are hosted by Taylor and Francis Online.
A new concept of fueling a liquid-metal fast breeder reactor (LMFBR) is proposed with the aims of increasing the resource base of nuclear energy for the generation of electricity and of resolving the safety question of current LMFBRs. The basic feature of the concept is the use of 233U/Th fuel in a central part of the LMFBR core and Pu/U fuel in the outer core. The reactor is flexible in its utilization of nuclear fuels and can be an efficient breeder reactor with either the uranium or the thorium cycle. The safety characteristics of the reactor are superior to those of plutonium-fueled LMFBRs of current designs with the sodium-void reactivities being negative almost everywhere in the core. The design and thermal characteristics of the proposed pins indicate that in the 233U/Th-fueled inner core, thick soft-spectrum pins can be advantageous over solid pins of a more conventional type.