ANALYSIS OF THE RE-CRITICALITY POTENTIAL DURING THE EARLY IN-VESSEL PHASE OF A STATION BLACKOUT IN A BWR REACTOR
Piotr Darnowski , K. Potapczyk , Grzegorz Niewiński , Michał Gatkowski
AbstractAnalysis of a potential for the re-criticality phenomenon occurrence during the core reflooding at the time of the early in-vessel phase of a Station Blackout in a BWR reactor was performed. The impact of the boron inventory in the water was studied. Investigated reactor design and accident sequence were based on the Fukushima-Daiichi Unit 3 (1F3). A STEP-3 9x9 BWR fuel design was selected and criticality safety calculations were prepared with the SERPENT Monte Carlo reactor physics code. The representative part of the core was simulated in three dimensions for the core unit cell composed of four fuel assemblies. The MELCOR severe accident computer code was used as a source of the thermal-hydraulic and the core state data. Obtained results show that the re-criticality was possible in the case of the complete control blades degradation and injection of the water with less than 250 ppm of boron.
|Publication size in sheets||0.5|
ENC 2016 Conference Proceedings, 2016, Brussels, European Nuclear Society, ISBN 978-92-95064-27-0, 448 p.
ENC2016-transactions.pdf / No licence information (file archived - login or check accessibility on faculty)
|Keywords in English||SERPENT; BWR|
|Score|| = 15.0, 05-09-2019, BookChapterMatConfByConferenceseries|
= 15.0, 05-09-2019, BookChapterMatConfByConferenceseries
* presented citation count is obtained through Internet information analysis and it is close to the number calculated by the Publish or Perish system.