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Deterministic and stochastic neutron cross-section generation for PARCS applied to VR-1 reactor

Authors: Filip Fejt;

Deterministic and stochastic neutron cross-section generation for PARCS applied to VR-1 reactor

Abstract

The VR-1 reactor operated by the Czech Technical University in Prague was utilized for a study of a macroscopic cross-sections homogenization performed by deterministic (SCALE 6.1.2 — Triton) and stochastic (Serpent 2.1.24) codes. These cross-sections are subsequently imported into a fixed source problem solved by the three-dimensional reactor core simulator PARCS v3.2. PARCS solves the steady-state and time-dependent, multi-group neutron diffusion and low order transport equations. All multiplication factors provided by each code are compared and discussed. Due to the small size of the core, all elements are more closely coupled by neutron fluxes in surrounding positions; therefore homogenization must be conducted in properly chosen volumes to respect all effects of a spatiality.

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selected citations
These citations are derived from selected sources.
This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Citations provided by BIP!
popularity
This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network.
BIP!Popularity provided by BIP!
influence
This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Influence provided by BIP!
impulse
This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network.
BIP!Impulse provided by BIP!
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