About: Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core

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An Entity of Type : http://linked.opendata.cz/ontology/domain/vavai/Vysledek, within Data Space : linked.opendata.cz associated with source document(s)

Attributes	Values
rdf:type	skos:Concept http://linked.opendata.cz/ontology/domain/vavai/Vysledek
rdfs:seeAlso	http://proceedings.asmedigitalcollection.asme.org/proceeding.aspx?articleid=1937236
Description	Research Centre Rez solves several safety related projects dealing with safety of Czech NPPs, some of which require fully functioning Three Dimensional (3D) model of the reactor core. While in a number of safety analysis of various accident scenarios it is sufficient to use one point reactor kinetics, there are selected types of accidents in which it is useful to model the space (3D) neutron kinetics, in particular control rod ejections, boron dilution scenarios, including transitions from design basis to beyond design basis accidents. This paper is focused to analyze the present model of the core of VVER1000/V320 reactor. Which is applicable for 3D modeling of neutron kinetics in selected design and beyond design basis accidents. The model is based on a cross-sections library created by SCALE 6.1.2/TRITON simulations. PARCS 3.2 code uses homogenized cross-sections libraries to calculate neutronic and other core parameters of the PWR reactors. Similar model is prepared with MCNP6 for comparison between deterministic (Pn spherical-harmonics method used in PARCS) and the stochastic (Monte Carlo) approach (used in MCNP6). Such comparison will serve as a demonstration of the capability of the PARCS code for VVER1000/V320 analyses. Research Centre Rez solves several safety related projects dealing with safety of Czech NPPs, some of which require fully functioning Three Dimensional (3D) model of the reactor core. While in a number of safety analysis of various accident scenarios it is sufficient to use one point reactor kinetics, there are selected types of accidents in which it is useful to model the space (3D) neutron kinetics, in particular control rod ejections, boron dilution scenarios, including transitions from design basis to beyond design basis accidents. This paper is focused to analyze the present model of the core of VVER1000/V320 reactor. Which is applicable for 3D modeling of neutron kinetics in selected design and beyond design basis accidents. The model is based on a cross-sections library created by SCALE 6.1.2/TRITON simulations. PARCS 3.2 code uses homogenized cross-sections libraries to calculate neutronic and other core parameters of the PWR reactors. Similar model is prepared with MCNP6 for comparison between deterministic (Pn spherical-harmonics method used in PARCS) and the stochastic (Monte Carlo) approach (used in MCNP6). Such comparison will serve as a demonstration of the capability of the PARCS code for VVER1000/V320 analyses. (en)
Title	Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core (en)
skos:prefLabel	Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core (en)
skos:notation	RIV/26722445:_____/14:#0000991!RIV15-MV0-26722445
http://linked.open...avai/riv/aktivita	P
http://linked.open...avai/riv/aktivity	P(EE2.3.30.0026), P(VG20132015105)
http://linked.open...vai/riv/dodaniDat	2015
http://linked.open...aciTvurceVysledku	Miglierini, Bruno Ruščák, Martin Mazzini, Guido
http://linked.open.../riv/druhVysledku	D - Článek ve sborníku
http://linked.open...iv/duvernostUdaju	S - Úplné a pravdivé údaje nepodléhající ochraně podle zvláštních právních předpisů
http://linked.open...titaPredkladatele	Centrum výzkumu Řež s.r.o.
http://linked.open...dnocenehoVysledku	7997
http://linked.open...ai/riv/idVysledku	RIV/26722445:_____/14:#0000991
http://linked.open...riv/jazykVysledku	eng - angličtina
http://linked.open.../riv/klicovaSlova	nuclear safety; 3D modelling; WWER type reactors (en)
http://linked.open.../riv/klicoveSlovo	nuclear safety WWER type reactors 3D modelling
http://linked.open...ontrolniKodProRIV	[D19B6AF19DE8]
http://linked.open...v/mistoKonaniAkce	Praha
http://linked.open...i/riv/mistoVydani	New York, USA
http://linked.open...i/riv/nazevZdroje	2014 22nd International Conference on Nuclear Engineering Volume 4
http://linked.open...in/vavai/riv/obor	JF
http://linked.open...ichTvurcuVysledku	3 (xsd:int)
http://linked.open...cetTvurcuVysledku	3 (xsd:int)
http://linked.open...vavai/riv/projekt	Prevention, preparedness and reduction of consequences of serious accidents of the Czech nuclear power plants in connection with the new experience obtained from the stress tests after the Fukushima accident Nuclear safety assessment knowledge basis development
http://linked.open...UplatneniVysledku	2014
http://linked.open...iv/tvurceVysledku	Mazzini, Guido Miglierini, Bruno Ruščák, Martin
http://linked.open...vavai/riv/typAkce	WRD - Světová
http://linked.open.../riv/zahajeniAkce	2014-01-01 (xsd:date)
number of pages	6 (xsd:int)
http://bibframe.org/vocab/doi	10.1115/ICONE22-30386
http://purl.org/ne...btex#hasPublisher	ASME
https://schema.org/isbn	978-0-7918-4594-3

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