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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
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.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Luis E. Herranz, José I. Linares, Beatriz Y. Moratilla
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 15-24
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3853
Articles are hosted by Taylor and Francis Online.
Future world energy demand will require a sustainable energy generation system. Optimization of power cycles has become a key element to better exploit natural resources, to minimize waste production, and even to reduce fuel cycle cost. Aware of this, nuclear technology is developing what has been termed Generation IV designs. In particular, the high-temperature gas-cooled reactor (HTGR) concept is a promising technology to reach much higher thermal efficiencies than present nuclear power plants.By using a classical thermodynamic methodology, this paper demonstrates that regenerative reheating would significantly enhance the thermal performance of a reference Brayton cycle based on pebble bed modular reactor (PBMR) technology. The regenerative reheating is conducted by a live gas fraction () extracted from the coolant inventory exiting the nuclear reactor. Optimization of results in efficiency values as high as 53 and 61%, respectively, under current and midterm technology scenarios. In addition, reheating would allow an effective and easy-to-conduct "load-follow" operation with no loss of thermal efficiency in the upper range of . Even further, under the midterm technology scenario, reheating would make it possible to cogenerate H2 from the enthalpy content of the fraction exiting reheater.