Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory
Author:
Funder
Nemzeti Kutatási, Fejlesztési és Innovaciós Alap
Publisher
Elsevier BV
Reference23 articles.
1. Calculation of the activity of fission products in the primary coolant of the eastern-type pressurized water reactor (VVER1000-V446) of the Bushehr Nuclear Power Plant at normal full power operational condition;Asadollahzadeh Goudarzi;Progress in Nuclear Energy,2015
2. Study on the production characteristics of 131I and 90Sr isotopes in a molten salt reactor;Chen;Nucl. Sci. Tech.,2021
3. Detection of Fuel Failure in Pressurized Water Reactor with Artificial Neural Network;Dong;Ann. Nucl. Energy.,2020
4. A general model for predicting coolant activity behaviour for fuel-failure monitoring analysis;El-Jaby;J. Nucl. Mater.,2010
5. Fuel Reliability Monitoring and Failure Evaluation Handbook (2010): Revision 2. EPRI, Palo, Alto, CA: 2010. 1019107. https://www-nds.iaea.org/relnsd/vcharthtml/VChartHTML.html.
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