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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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2024: The Year in Nuclear—April through June
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from April through May 2024.
Stay tuned for the top stories from the rest of the past year.
Masato Takahashi
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 230-240
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3218
Articles are hosted by Taylor and Francis Online.
A new method for off-gas source estimation in plants with nondefective fuel is proposed. This method based on the activity ratio between 138Xe and 88Kr is able to directly estimate the off-gas source using only measurement data. The 138Xe to 88Kr activity ratio is decided on the basis of the fissile irradiation with the different neutron spectrum in the core region and the fission fragment emission rate into coolant. This method was applied to actual plant data, and it was demonstrated that the dominant source of off-gas in a plant with nondefective fuel is Pu produced by the burnup of uranium impurities in the core structure. The concentration of uranium impurities in cladding estimated by this method is consistent with the result of neutron activation analysis.
