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3D Analysis of a multipurpose modular reactor for small energy production
Author(s) -
Şahin Sümer,
Şarer Başar
Publication year - 2020
Publication title -
international journal of energy research
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.808
H-Index - 95
eISSN - 1099-114X
pISSN - 0363-907X
DOI - 10.1002/er.5453
Subject(s) - light water reactor , coolant , materials science , nuclear engineering , cladding (metalworking) , graphite , rod , criticality , nuclear reactor core , nuclear fuel , pressurized water reactor , nuclear physics , composite material , engineering , physics , medicine , alternative medicine , pathology
Summary The Fixed Bed Nuclear Reactor (FBNR) is a modular reactor for small energy needs (70‐120 MW el ). FBNR is pressurized water reactor, but uses GEN‐IV reactors fuel. UO 2 kernels of 500 μm diameter with 25 μm thick SiC cladding are embedded in graphite matrix form the spherical fuel elements with a diameter of 15 mm and covered by 300 μm thick Zircaloy‐4 cladding. FBNR has high level safety features and operates without On‐site Refueling. Approximately 1.62 million spherical fuel elements are suspended in a core height of 200 cm and inner and outer diameters of 32 cm and 224 cm by upwards flowing light water coolant with 280°C entry and 340°C exit temperatures. The unit lattice geometry is dodecahedron with fuel element in center and surrounded with light water coolant‐moderator.In the present work, 9% enriched UO 2 fuel is used. Neutronic analysis has been performed with the MCNPX‐2.7.0 code. As, it is not practical to tackle millions of fuel elements separately, at first run unit fuel cell calculations are performed in spherical geometry for one single lattice consisting of separate fuel, cladding and volume‐equivalent moderator regions. In the second run, the fuel cell is homogenized. Infinite cell calculations have been executed for variable moderator/fuel (H/ 235 U) ratios in order to determine under‐ and over‐moderated criticality values. The criticality values for the homogenized cell geometry are slightly lower and remains <5% range, that is, on the conservative side, which is acceptable for the purpose of this study. This allows us to homogenize the entire core for the full 3‐D reactor with core and reflector regions. Reactor criticality increases with increasing H/ 235 U ratios in the, under moderated region, where H/ 235 U = 18 is selected for further investigations. Temporal variation of the reactor criticality is pursued for full reactor power of 210 MW th (~70 MW el net) with k eff = 1.36 at the beginning of life down to k eff = 1.02 over 1260 days with a plant factor of 1.0. The final fuel burn up was found as 57.3 GWd/ton.