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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Geological work begins on Poland’s first nuclear plant
Project management firm Bechtel started site geological surveys for Poland’s first nuclear power plant project, the company announced on Wednesday.
Bechtel will conduct in-depth geological surveys at the Lubiatowo-Kopalino site in the Pomeranian municipality of Choczewo, in northern Poland. This is a key milestone for the country’s entry into nuclear power production, as the surveys will inform the suitability of the planned site.
J. Krejčí, V. Vrtílková, J. Kabátová, A. Přibyl, P. Gajdoš, D. Rada, J. Šustr
Nuclear Technology | Volume 201 | Number 1 | January 2018 | Pages 52-65
Technical Paper | doi.org/10.1080/00295450.2017.1389595
Articles are hosted by Taylor and Francis Online.
High-temperature oxidation of WWER fuel cladding under loss-of-coolant accident conditions represents a significant problem and an issue of ongoing study. A study of oxidation kinetics under high-temperature steam oxidation was carried out on a sponge-based E110 cladding tube material in as-received state and exposed to a temperature range between 600°C and 1300°C. Metallographic evaluation of the samples was used to determine the analytical dependencies of the processes of the oxide layer and the oxygen stabilized alpha-zirconium layer formation.
The formation of this oxide layer and the layer under the oxide (oxygen stabilized alpha-zirconium) was usually considered to follow a parabolic rate law (e.g., Cathcart-Pawel for Zircaloy, and Solyany for iodide/electrolytic E110), however, the recently performed UJP PRAHA a.s. (UJP) experiments showed different kinetics for oxide layers in the whole temperature range between 600°C and 1300°C. The metallographic evaluation showed changing kinetics of oxide layer formation for several temperatures. Therefore, a new oxide layer formation kinetics, different from the parabolic law, was designed. The parabolic rate law was optimized for the oxygen stabilized alpha-zirconium, which is applicable in the temperature range between 950°C and 1300°C.
The UJP experimental database containing more than 1000 data values was compared with the newly developed UJP correlations and other available correlations for iodide/electrolytic E110 and Zircaloy alloys. The UJP correlation for weight gain kinetics was compared with experimental data from different laboratories. Finally, a statistical analysis of all tested correlations is provided.