First experience with a six-loop nodalization of a VVER-440 using a new coupled neutronic-thermohydraulics system KIKO3D-RETINA V1.1D

István Farkas, G. Házi, Gusztáv Mayer, András Keresztúri, György Hegyi, István Panka

Research output: Contribution to journalArticle

5 Citations (Scopus)

Abstract

In this paper, we introduce a new, coupled neutronic-thermohydraulics system. The three-dimensional neutron kinetic code KIKO3D and the two-phase flow code RETINA V1.1D have been coupled for modeling complex transients of nuclear power plants. Using a six-loop nodalization of a VVER-440, several test calculations have been carried out. Results obtained for a trip of one main circulation pump are compared with real measurements and reference calculations provided by other neutronic-thermohydraulics systems. The ability of our coupled system is demonstrated.

Original languageEnglish
Pages (from-to)2235-2242
Number of pages8
JournalAnnals of Nuclear Energy
Volume29
Issue number18
DOIs
Publication statusPublished - Dec 2002

Fingerprint

two phase flow
nuclear power plant
Two phase flow
Nuclear power plants
pump
Neutrons
Pumps
kinetics
Kinetics
modeling
code
calculation
test

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Waste Management and Disposal

Cite this

First experience with a six-loop nodalization of a VVER-440 using a new coupled neutronic-thermohydraulics system KIKO3D-RETINA V1.1D. / Farkas, István; Házi, G.; Mayer, Gusztáv; Keresztúri, András; Hegyi, György; Panka, István.

In: Annals of Nuclear Energy, Vol. 29, No. 18, 12.2002, p. 2235-2242.

Research output: Contribution to journalArticle

Farkas, István ; Házi, G. ; Mayer, Gusztáv ; Keresztúri, András ; Hegyi, György ; Panka, István. / First experience with a six-loop nodalization of a VVER-440 using a new coupled neutronic-thermohydraulics system KIKO3D-RETINA V1.1D. In: Annals of Nuclear Energy. 2002 ; Vol. 29, No. 18. pp. 2235-2242.
@article{c9c73a3bdda44d8194e4f47c474c9964,
title = "First experience with a six-loop nodalization of a VVER-440 using a new coupled neutronic-thermohydraulics system KIKO3D-RETINA V1.1D",
abstract = "In this paper, we introduce a new, coupled neutronic-thermohydraulics system. The three-dimensional neutron kinetic code KIKO3D and the two-phase flow code RETINA V1.1D have been coupled for modeling complex transients of nuclear power plants. Using a six-loop nodalization of a VVER-440, several test calculations have been carried out. Results obtained for a trip of one main circulation pump are compared with real measurements and reference calculations provided by other neutronic-thermohydraulics systems. The ability of our coupled system is demonstrated.",
author = "Istv{\'a}n Farkas and G. H{\'a}zi and Guszt{\'a}v Mayer and Andr{\'a}s Kereszt{\'u}ri and Gy{\"o}rgy Hegyi and Istv{\'a}n Panka",
year = "2002",
month = "12",
doi = "10.1016/S0306-4549(02)00037-3",
language = "English",
volume = "29",
pages = "2235--2242",
journal = "Annals of Nuclear Energy",
issn = "0306-4549",
publisher = "Elsevier Limited",
number = "18",

}

TY - JOUR

T1 - First experience with a six-loop nodalization of a VVER-440 using a new coupled neutronic-thermohydraulics system KIKO3D-RETINA V1.1D

AU - Farkas, István

AU - Házi, G.

AU - Mayer, Gusztáv

AU - Keresztúri, András

AU - Hegyi, György

AU - Panka, István

PY - 2002/12

Y1 - 2002/12

N2 - In this paper, we introduce a new, coupled neutronic-thermohydraulics system. The three-dimensional neutron kinetic code KIKO3D and the two-phase flow code RETINA V1.1D have been coupled for modeling complex transients of nuclear power plants. Using a six-loop nodalization of a VVER-440, several test calculations have been carried out. Results obtained for a trip of one main circulation pump are compared with real measurements and reference calculations provided by other neutronic-thermohydraulics systems. The ability of our coupled system is demonstrated.

AB - In this paper, we introduce a new, coupled neutronic-thermohydraulics system. The three-dimensional neutron kinetic code KIKO3D and the two-phase flow code RETINA V1.1D have been coupled for modeling complex transients of nuclear power plants. Using a six-loop nodalization of a VVER-440, several test calculations have been carried out. Results obtained for a trip of one main circulation pump are compared with real measurements and reference calculations provided by other neutronic-thermohydraulics systems. The ability of our coupled system is demonstrated.

UR - http://www.scopus.com/inward/record.url?scp=0036885231&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=0036885231&partnerID=8YFLogxK

U2 - 10.1016/S0306-4549(02)00037-3

DO - 10.1016/S0306-4549(02)00037-3

M3 - Article

VL - 29

SP - 2235

EP - 2242

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

SN - 0306-4549

IS - 18

ER -