NEUTRONIC ANALYSIS OF THE CANDIDATE MULTI-LAYER CLADDING MATERIALS WITH ENHANCED ACCIDENT TOLERANCE FOR WWER REACTORS

Authors

  • Ondřej Novák Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Prague, Czech Republic, V Holešovickách 2, Prague 8, Czech Republic
  • Martin Ševeček

DOI:

https://doi.org/10.14311/APP.2018.14.0027

Keywords:

WWER, Nuclear Fuel, Cladding, Accident Tolerant Fuel, Neutronics, Serpent

Abstract

The paper summarizes preliminary results of neutronic analysis of candidate ATF cladding materials that are under development at the CTU in Prague. To evaluate basic neutronics-related characteristics the Serpent code was used which is a Monte-Carlo based simulation tool. A model of WWER fuel was developed and basic neutronic analysis performed. All coating materials entail certain reactivity penalty compared to reference uncoated cladding that was quantified. The coating of cladding affects also other neutron-physical parameters of cores that modify the performance of the WWER reactors that are discussed.

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Published

2018-05-17

How to Cite

Novák, O., & Ševeček, M. (2018). NEUTRONIC ANALYSIS OF THE CANDIDATE MULTI-LAYER CLADDING MATERIALS WITH ENHANCED ACCIDENT TOLERANCE FOR WWER REACTORS. Acta Polytechnica CTU Proceedings, 14, 27–33. https://doi.org/10.14311/APP.2018.14.0027

Issue

Vol. 14 (2018): ŠIMÁNĚ 2017

Section

Articles