ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Tatjana Jevremovic, Yoshiaki Oka, Sei-Ichi Koshizuka
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 273-284
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35232
Articles are hosted by Taylor and Francis Online.
The core design of a fast converter reactor adopting enriched UO2 fuel is studied for maximizing the power rating of the direct-cycle, supercritical water-cooled fast reactor with the same reactor pressure vessel as the breeder and mixed-oxide (MOX) fueled converter. The coolant void reactivity is kept negative by placing thin zirconium-hydride layers in the blanket fuel assemblies facing the driver fuels, as in our fast breeder reactor design. Compared with the fast converter adopting MOX fuel, the electric power output is increased 11%, from 1444 to 1625 MW(electric). It is attained by the reduced blanket fuel fraction for keeping negative reactivity at coolant voiding. The positive reactivity at flooding the core is much larger than that of the MOX core, but it can be managed by the control rod system. The conversion ratio, the surviving ratio, is 0.85, reduced 0.1 from that of the MOX converter. The enrichment of UO2fuel reaches 16.9%. The specific fissile inventory is the highest, compared with the MOX-fueled converter and breeder due to the lower fission cross sections of 235U. The cores of the supercritical water-cooled reactors are radially heterogeneous. The decoupling problem is, however, much smaller than that of the liquid-metal fast breeder reactor due to the smaller core diameter. The hydrogen loss from the zirconium hydrides at steady state and accidental conditions does not impose a problem.