SIMULATIONS OF THE AP1000-BASED REACTOR CORE WITH SERPENT COMPUTER CODE
Piotr Darnowski , Patryk Ignaczak , Paweł Obrębski , Michał Stępień , Grzegorz Niewiński
AbstractThe paper presents the core design, model development and results of the neutron transport simulations of the large Pressurized Water Reactor based on the AP1000 de- sign. The SERPENT 2.1.29 Monte Carlo reactor physics computer code with ENDF/B- VII and JEFF 3.1.1 nuclear data libraries was applied. The full-core 3D models were developed according to the available Design Control Documentation and the literature. Criticality simulations were performed for the core at the Beginning of Life state for Cold Shutdown, Hot Zero Power and Full Power conditions. Selected core parameters were investigated and compared with the design data: eﬀective multiplication factors, boron concentrations, control rod worth, reactivity coeﬃcients and radial power dis- tributions. Acceptable agreement between design data and simulations was obtained, conﬁrming the validity of the model and applied methodology.
|Journal series||Archive of Mechanical Engineering, [Archiwum Budowy Maszyn], ISSN 0004-0738, e-ISSN 2300-1895, (B 15 pkt)|
|Publication size in sheets||1.5|
|Keywords in English||Monte Carlo, SERPENT, AP1000, PWR, nuclear reactor|
|Score||= 15.0, 24-01-2020, ArticleFromJournal|
|Publication indicators||= 0; = 0; = 1.0; : 2018 = 0.69|
|Citation count*||1 (2020-02-16)|
* presented citation count is obtained through Internet information analysis and it is close to the number calculated by the Publish or Perish system.