Publication detail

VALIDATION STUDY OF FUEL ASSEMBLY MODEL OF VVER 1000 REACTOR BY TRITON

VOJÁČKOVÁ, J. ŠTEVANKA, K. KATOVSKÝ, K. FORAL, Š. HERALECKÝ, P.

Original Title

VALIDATION STUDY OF FUEL ASSEMBLY MODEL OF VVER 1000 REACTOR BY TRITON

English Title

VALIDATION STUDY OF FUEL ASSEMBLY MODEL OF VVER 1000 REACTOR BY TRITON

Type

conference proceedings

Language

en

Original Abstract

This paper describes the fuel assembly model of VVER 1000 reactor. This model was developed based on document In-core fuel management code package validation for WWERs. The fuel assembly of Kalinin Unit 1 is described in document. The fuel assembly model has been created by reactor physics analysis tool TRITON (Code package Scale 6.2). The fuel assembly model has been validated by the results of benchmark participation and model of Monte Carlo code Keno. Several cases with different fuel, moderator and cladding temperature, enrichment, boron concentration in moderator were calculated. The depletation calculation has been also computed. The newest cross section library ENDF/B-VI. 252 neutron groups has been used for calculation. The impact of used cross section libraries to results has been discussed in this paper. The model of fuel assembly in TRITON will be used for generating macroscopic cross section library for further simulation in nodal code PARCS. Coupled calculation of nodal code and thermal hydraulic code is necessary for safety analyses with nonsymmetrical power distribution in the core. This report describe the results of second part of knowledge transfer project between Brno University of Technology and company TES. This report will support certification of computation tool for safety analyses.

English abstract

This paper describes the fuel assembly model of VVER 1000 reactor. This model was developed based on document In-core fuel management code package validation for WWERs. The fuel assembly of Kalinin Unit 1 is described in document. The fuel assembly model has been created by reactor physics analysis tool TRITON (Code package Scale 6.2). The fuel assembly model has been validated by the results of benchmark participation and model of Monte Carlo code Keno. Several cases with different fuel, moderator and cladding temperature, enrichment, boron concentration in moderator were calculated. The depletation calculation has been also computed. The newest cross section library ENDF/B-VI. 252 neutron groups has been used for calculation. The impact of used cross section libraries to results has been discussed in this paper. The model of fuel assembly in TRITON will be used for generating macroscopic cross section library for further simulation in nodal code PARCS. Coupled calculation of nodal code and thermal hydraulic code is necessary for safety analyses with nonsymmetrical power distribution in the core. This report describe the results of second part of knowledge transfer project between Brno University of Technology and company TES. This report will support certification of computation tool for safety analyses.

Keywords

VVER 1000; TRITON; PARCS; fuel assembly; validation

Released

26.04.2018

Publisher

American Nuclear Society

ISBN

978-0-89448-762-2

Book

PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems

Edition

1

Edition number

1

Pages from

400

Pages to

405

Pages count

6

Documents

BibTex


@proceedings{BUT148639,
  author="Jitka {Vojáčková} and Kamil {Števanka} and Karel {Katovský} and Štěpán {Foral} and Petr {Heralecký}",
  title="VALIDATION STUDY OF FUEL ASSEMBLY MODEL OF VVER 1000 REACTOR BY TRITON",
  annote="This paper describes the fuel assembly model of VVER 1000 reactor. This model was developed based on document In-core fuel management code package validation for WWERs. The fuel assembly of Kalinin Unit 1 is described in document. The fuel assembly model has been created by reactor physics analysis tool TRITON (Code package Scale 6.2). The fuel assembly model has been validated by the results of benchmark participation and model of Monte Carlo code Keno. Several cases with different fuel, moderator and cladding temperature, enrichment, boron concentration in moderator were calculated. The depletation calculation has been also computed. The newest cross section library ENDF/B-VI. 252 neutron groups has been used for calculation. The impact of used cross section libraries to results has been discussed in this paper. The model of fuel assembly in TRITON will be used for generating macroscopic cross section library for further simulation in nodal code PARCS. Coupled calculation of nodal code and thermal hydraulic code is necessary for safety analyses with nonsymmetrical power distribution in the core. This report describe the results of second part of knowledge transfer project between Brno University of Technology and company TES. This report will support certification of computation tool for safety analyses.",
  address="American Nuclear Society",
  booktitle="PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems",
  chapter="148639",
  edition="1",
  howpublished="electronic, physical medium",
  institution="American Nuclear Society",
  year="2018",
  month="april",
  pages="400--405",
  publisher="American Nuclear Society",
  type="conference proceedings"
}