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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
UMich introductory engineering course aims to revolutionize nuclear energy through community engagement
A new course at the University of Michigan offered by the Nuclear Engineering and Radiological Sciences (NERS) Department seeks to address the lack of community engagement in the design of energy technologies by pioneering a socially engaged approach.
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.