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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NWMO to select Canadian repository site this year
Canada’s Nuclear Waste Management Organization, a not-for-profit organization responsible for the long-term management of the country’s intermediate- and high-level radioactive waste, is set to select a site for a deep geologic repository by the end of the year.
Tetsuya Mouri, Shuhei Maruyama, Taira Hazama, Takayuki Suzuki
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 286-307
Technical Note | Fission Reactors | doi.org/10.13182/NT12-A14099
Articles are hosted by Taylor and Francis Online.
The present technical note describes the evaluation of the isothermal temperature coefficient data obtained in the Monju restart core. As in the preceding evaluations on the criticality and the control rod worth, the best-estimate value and its uncertainty are evaluated as accurately as possible. Data obtained in the previous test are evaluated in the same level of detail.The measured data show that the fuel composition change from the previous test decreases the magnitude of the temperature coefficient by [approximately]8%. Through a sensitivity analysis, it is confirmed that the decrease is mainly brought by the composition of 241Pu and 241Am.The best calculation accuracy within the experimental uncertainty of 2% is attained with JENDL-4.0 for the previous core; however, such a good accuracy is not achieved for the restart core. A further experimental investigation is required to solve the dependence of calculation accuracy on the core configurations.