Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor
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DOI: 10.1007/s10512-017-0259-3
Abstract: A comparative analysis is made of calculations of a loss-of-coolant accident in a 1500 MW(t) fast reactor. The COREMELT code with different neutron-physical modules RADAR3D and RAKAR2D and the same thermohydraulic module COREMELT are used.… read more here.
Keywords: serious accident; sodium; accident; fast reactor ... See more keywords
Reactivity Runaway Reduction When Using Enriched Uranium in a Lead Fast Reactor
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DOI: 10.1007/s10512-018-0379-4
Abstract: The possibilities for reactivity runaway reduction in a fast reactor when using enriched uranium are examined. Specifically, an approach supposing partial compensation of reactivity runaway by the addition of Np or Am, as consumable absorbers,… read more here.
Keywords: enriched uranium; runaway reduction; fast reactor; reactivity runaway ... See more keywords
Homogenous Transmutation of 237Np, 241Am, 243Am in a Lead-Cooled Fast Reactor
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DOI: 10.1007/s10512-021-00756-1
Abstract: The results of a study of the effect of the homogeneous addition of 237Np, 241Am, 243Am into the fuel on the neutronics characteristics of a lead-cooled fast reactor are reported. The reasons for the change… read more here.
Keywords: 241am 243am; fast reactor; cooled fast; 237np 241am ... See more keywords
Modifier-free separation of trivalent actinides and lanthanides from fast reactor simulated high-level liquid waste using N,N-di-octyl-2-hydroxyacetamide
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DOI: 10.1007/s10967-017-5528-z
Abstract: The extraction behaviour of Am(III) and other metal ions present in the fast reactor simulated high- level liquid waste (FR-SHLLW) was studied using a modifier-free solvent phase composed of N,N-di-octyl-2-hydroxyacetamide (DOHyA) in n-dodecane. Quantitative extraction… read more here.
Keywords: iii; high level; simulated high; reactor simulated ... See more keywords
Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor
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DOI: 10.1016/j.anucene.2016.09.025
Abstract: Abstract Minor actinide (MA) accumulated in spent fuel is the primary contributor to the long-term radiological hazards of high-level nuclear waste. Due to its outstanding features such as fast neutron spectrum, no fuel assembly fabrication,… read more here.
Keywords: minor actinide; molten salt; 233 extraction; fast reactor ... See more keywords
Investigation on the potential use of thorium as fuel for the Sodium-cooled Fast Reactor
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DOI: 10.1016/j.anucene.2017.01.030
Abstract: Generation IV reactors are planned to be an evolutionary step in the history of nuclear power plants. Although they have many advantageous properties, five of the six concepts are designed for the utilization of uranium–plutonium… read more here.
Keywords: thorium; fuel; fast reactor; cooled fast ... See more keywords
Benchmark and demonstration of the CHD code for transient analysis of fast reactor systems
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DOI: 10.1016/j.anucene.2017.05.031
Abstract: Abstract In this paper the dynamic thermal hydraulic fast reactor simulation code CHD is presented. The code is built around a scriptable object-oriented framework in the programming language Python to be able to flexibly describe… read more here.
Keywords: benchmark demonstration; chd code; code; fast reactor ... See more keywords
Performance assessment of adjusted nuclear data along with their covariances on the basis of fast reactor experiments
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DOI: 10.1016/j.anucene.2018.07.043
Abstract: Abstract In view of fast reactor analyses, it is shown that efficient nuclear data adjustments can be obtained on a limited assimilation database consisting of just six well documented integral parameters, i.e. the central spectral… read more here.
Keywords: fast reactor; performance; jeff tendl; nuclear data ... See more keywords
Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data
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DOI: 10.1016/j.anucene.2019.01.057
Abstract: Abstract In view of precise fast reactor analyses, we find that the Asymptotic Progressing Incremental nuclear data Adjustment (APIA) methodology described in previous papers is able providing particularly useful, consistent adjustments by assimilating the integral… read more here.
Keywords: methodology; nuclear data; fast reactor; adjustment apia ... See more keywords
Performance analysis of magnetohydrodynamic pump for sodium-cooled fast reactor thermal hydraulic experiment
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DOI: 10.1016/j.anucene.2019.04.037
Abstract: Abstract An MHD pump with a developed pressure of 4 bar and flow rate of 20 kg/s was designed using electrical equivalent circuit method, which is typically used in analyzing linear induction machines. The experiment is conducted… read more here.
Keywords: cooled fast; sodium cooled; pump; reactor thermal ... See more keywords
Preliminary investigation on the melting behavior of a freeze-valve for the Molten Salt Fast Reactor
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DOI: 10.1016/j.anucene.2019.06.039
Abstract: Abstract This paper focuses on the freeze-plug, a key safety component of the Molten Salt Fast Reactor, one of the Gen. IV nuclear reactors that must excel in safety, reliability, and sustainability. The freeze-plug is… read more here.
Keywords: freeze; plug; fast reactor; molten salt ... See more keywords