Non-Free Swelling of Uranium Dioxide Fuel at Burnup 8–13% h.a.
Sign Up to like & getrecommendations! Published in 2017 at "Atomic Energy"
DOI: 10.1007/s10512-017-0192-5
Abstract: The porosity and rate of non-free swelling of the fuel in fast-reactor fuel elements with EK-164ID c.d. steel cladding were measured by hydrostatic and metallographic methods. It was shown that the rate of swelling of… read more here.
Keywords: swelling uranium; free swelling; uranium dioxide; non free ... See more keywords
Simulation of the Effect of Burnup of Materials of an Ionization-Chamber Radiator by the Monte Carlo Method
Sign Up to like & getrecommendations! Published in 2017 at "Journal of Engineering Physics and Thermophysics"
DOI: 10.1007/s10891-017-1683-x
Abstract: Using the Monte Carlo method, the authors have modeled the burnup of fissionable material of the radiator of an ionization chamber in a neutron flux. A study has been made of the change in the… read more here.
Keywords: carlo method; monte carlo; burnup; radiator ... See more keywords
Statistical error propagation in HTR burnup model
Sign Up to like & getrecommendations! Published in 2017 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.03.039
Abstract: Abstract In this study we use independent replica calculations in order to assess statistical error propagation in whole-core actinide-burner High Temperature Reactor model. We use the MCB5 code for modeling a single irradiation cycle with… read more here.
Keywords: error propagation; burnup; model; statistical error ... See more keywords
Depletion chain optimization of lattice code STREAM for LWR fuel assembly burnup analysis
Sign Up to like & getrecommendations! Published in 2019 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2018.08.030
Abstract: Abstract A depletion chain simplification method is applied to UNIST lattice code STREAM (Steady state and Transient REactor Analysis code with Method of Characteristics) in this paper to alleviate the computational burden of depletion calculation… read more here.
Keywords: chain; burnup; fuel; code ... See more keywords
The application of the DEM-based burnup construction method in the pebble burnup history analysis in HTR-10
Sign Up to like & getrecommendations! Published in 2019 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2019.04.013
Abstract: Abstract In the 10 MW high temperature gas-cooled test reactor (HTR-10) operation history, the reactor experienced frequent shutdown periods and irradiation periods with varied power. The complicated operation history is supposed to influence the pebble burnup… read more here.
Keywords: pebble burnup; burnup; method; operation history ... See more keywords
Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration
Sign Up to like & getrecommendations! Published in 2021 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2021.111339
Abstract: Abstract Modeling and burnup analysis of Uranium dioxide ( U O 2 ) and Mixed Oxide (MOX) fuel in square assemblies comprising both solid and annular rods was carried out. The lattice pitch of the… read more here.
Keywords: burnup; mox fuel; fuel; annular rod ... See more keywords
Coupled Monte Carlo-burnup and CFD analysis of coated UN and UC fuels in an HPLWR fuel assembly
Sign Up to like & getrecommendations! Published in 2020 at "Progress in Nuclear Energy"
DOI: 10.1016/j.pnucene.2020.103342
Abstract: Abstract Ceramic nuclear fuels may have potential benefits to be considered as nuclear fuels in future Supercritical Water Reactors (SCWR), they offer the advantage of high thermal conductivity and high-density values compared to uranium dioxide.… read more here.
Keywords: fuel assembly; analysis; monte carlo; burnup ... See more keywords
Burnup Performance of CANDLE Burning Reactor Using Sodium Coolant
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DOI: 10.1080/00295639.2020.1775433
Abstract: Abstract The CANDLE (Constant Axial shape of Neutron flux, nuclide densities and power shape During Life of Energy production) reactor concept was proposed to overcome the disadvantages of current reactor technologies. In this study, a… read more here.
Keywords: burnup performance; sodium coolant; burnup; using sodium ... See more keywords