Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core

Elina Syrjälahti (Corresponding Author), Timo Ikonen, Ville Tulkki

Research output: Contribution to journalArticleScientificpeer-review

2 Citations (Scopus)

Abstract

This paper describes the simplified model for burnup-induced fuel rod deformations occurring during base irradiation period, from manufacturing to the beginning of the transient. Model is intended to be used together with a codes that are used for analysis of whole core and plant transients. Model consist of thermal and mechanical parts. Due to the high conductance approximation for the gap conductance, the thermal part of the model can be solved independently from the mechanical model. In this way the use of iterative solvers is avoided and model is simple to implement. Model is verified against FRAPCON simulations and has been integrated to the reactor dynamics code HEXTRAN, in which it provides initial data for fuel behavior module FINIX for transient simulation. Effect of burnup initialization on simulation of reactor transients has been demonstrated with the reactor dynamics code HEXTRAN that uses FINIX as a fuel behavior module.
Original languageEnglish
Pages (from-to)121-131
Number of pages11
JournalAnnals of Nuclear Energy
Volume125
DOIs
Publication statusPublished - 2019
MoE publication typeA1 Journal article-refereed

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Reactor cores
Irradiation

Keywords

  • Fuel rod behavior
  • Nuclear fuel modeling
  • Reactor dynamics
  • FINIX
  • HEXTRAN

Cite this

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title = "Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core",
abstract = "This paper describes the simplified model for burnup-induced fuel rod deformations occurring during base irradiation period, from manufacturing to the beginning of the transient. Model is intended to be used together with a codes that are used for analysis of whole core and plant transients. Model consist of thermal and mechanical parts. Due to the high conductance approximation for the gap conductance, the thermal part of the model can be solved independently from the mechanical model. In this way the use of iterative solvers is avoided and model is simple to implement. Model is verified against FRAPCON simulations and has been integrated to the reactor dynamics code HEXTRAN, in which it provides initial data for fuel behavior module FINIX for transient simulation. Effect of burnup initialization on simulation of reactor transients has been demonstrated with the reactor dynamics code HEXTRAN that uses FINIX as a fuel behavior module.",
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author = "Elina Syrj{\"a}lahti and Timo Ikonen and Ville Tulkki",
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Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core. / Syrjälahti, Elina (Corresponding Author); Ikonen, Timo; Tulkki, Ville.

In: Annals of Nuclear Energy, Vol. 125, 2019, p. 121-131.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core

AU - Syrjälahti, Elina

AU - Ikonen, Timo

AU - Tulkki, Ville

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N2 - This paper describes the simplified model for burnup-induced fuel rod deformations occurring during base irradiation period, from manufacturing to the beginning of the transient. Model is intended to be used together with a codes that are used for analysis of whole core and plant transients. Model consist of thermal and mechanical parts. Due to the high conductance approximation for the gap conductance, the thermal part of the model can be solved independently from the mechanical model. In this way the use of iterative solvers is avoided and model is simple to implement. Model is verified against FRAPCON simulations and has been integrated to the reactor dynamics code HEXTRAN, in which it provides initial data for fuel behavior module FINIX for transient simulation. Effect of burnup initialization on simulation of reactor transients has been demonstrated with the reactor dynamics code HEXTRAN that uses FINIX as a fuel behavior module.

AB - This paper describes the simplified model for burnup-induced fuel rod deformations occurring during base irradiation period, from manufacturing to the beginning of the transient. Model is intended to be used together with a codes that are used for analysis of whole core and plant transients. Model consist of thermal and mechanical parts. Due to the high conductance approximation for the gap conductance, the thermal part of the model can be solved independently from the mechanical model. In this way the use of iterative solvers is avoided and model is simple to implement. Model is verified against FRAPCON simulations and has been integrated to the reactor dynamics code HEXTRAN, in which it provides initial data for fuel behavior module FINIX for transient simulation. Effect of burnup initialization on simulation of reactor transients has been demonstrated with the reactor dynamics code HEXTRAN that uses FINIX as a fuel behavior module.

KW - Fuel rod behavior

KW - Nuclear fuel modeling

KW - Reactor dynamics

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