Modelling the transport in the porous layer of oxide films formed on material surfaces in nuclear power plants: A BWR case study

Jarmo Lehikoinen, Markus Olin

Research output: Book/ReportReport

2 Citations (Scopus)

Abstract

The deposited, porous layer of the oxide film adjacent to the bulk coolant is expected to have an impact on the activity incorporation (mainly by 60Co, which constitutes a major radiation hazard during shutdown maintenance due to its long half-life) into the structural materials of the primary circuit of nuclear power plants. This work aims at describing the steady-state transport of radioactive and other molecular species through the porous film with a mathematical model, and identifying the limiting phases for the rate of activity build-up from high-temperature aqueous solutions. A necessary prerequisite for gaining a lucid insight into the processes taking place in such systems is a reasonable characterization of the electrical atmosphere within the pore fluid, which is bound to greatly affect the transport properties of the soluble constituents therein. A BWR coolant with high-purity water under NWC conditions was selected as a test problem. It is the simplest case available for performing scoping calculations, yet relevant to actual high-temperature systems. A concise outline of a simple conceptualization of this particular transport system along with its mathematical description are given is this report. Preliminary model results are also presented and briefly discussed.
Original languageEnglish
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Number of pages34
ISBN (Print)951-38-5764-6
Publication statusPublished - 2000
MoE publication typeNot Eligible

Publication series

SeriesVTT Tiedotteita - Meddelanden - Research Notes
Number2062
ISSN1235-0605

Fingerprint

nuclear power plants
coolants
oxide films
radiation hazards
shutdowns
half life
maintenance
mathematical models
purity
transport properties
aqueous solutions
porosity
atmospheres
fluids
water

Keywords

  • nuclear power plants
  • BWR type reactors
  • corrosion
  • oxide films
  • high temperature
  • solutions
  • hematite
  • adsorption
  • complexation
  • transport modelling

Cite this

Lehikoinen, J., & Olin, M. (2000). Modelling the transport in the porous layer of oxide films formed on material surfaces in nuclear power plants: A BWR case study. Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Meddelanden - Research Notes, No. 2062
Lehikoinen, Jarmo ; Olin, Markus. / Modelling the transport in the porous layer of oxide films formed on material surfaces in nuclear power plants : A BWR case study. Espoo : VTT Technical Research Centre of Finland, 2000. 34 p. (VTT Tiedotteita - Meddelanden - Research Notes; No. 2062).
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Lehikoinen, J & Olin, M 2000, Modelling the transport in the porous layer of oxide films formed on material surfaces in nuclear power plants: A BWR case study. VTT Tiedotteita - Meddelanden - Research Notes, no. 2062, VTT Technical Research Centre of Finland, Espoo.

Modelling the transport in the porous layer of oxide films formed on material surfaces in nuclear power plants : A BWR case study. / Lehikoinen, Jarmo; Olin, Markus.

Espoo : VTT Technical Research Centre of Finland, 2000. 34 p. (VTT Tiedotteita - Meddelanden - Research Notes; No. 2062).

Research output: Book/ReportReport

TY - BOOK

T1 - Modelling the transport in the porous layer of oxide films formed on material surfaces in nuclear power plants

T2 - A BWR case study

AU - Lehikoinen, Jarmo

AU - Olin, Markus

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N2 - The deposited, porous layer of the oxide film adjacent to the bulk coolant is expected to have an impact on the activity incorporation (mainly by 60Co, which constitutes a major radiation hazard during shutdown maintenance due to its long half-life) into the structural materials of the primary circuit of nuclear power plants. This work aims at describing the steady-state transport of radioactive and other molecular species through the porous film with a mathematical model, and identifying the limiting phases for the rate of activity build-up from high-temperature aqueous solutions. A necessary prerequisite for gaining a lucid insight into the processes taking place in such systems is a reasonable characterization of the electrical atmosphere within the pore fluid, which is bound to greatly affect the transport properties of the soluble constituents therein. A BWR coolant with high-purity water under NWC conditions was selected as a test problem. It is the simplest case available for performing scoping calculations, yet relevant to actual high-temperature systems. A concise outline of a simple conceptualization of this particular transport system along with its mathematical description are given is this report. Preliminary model results are also presented and briefly discussed.

AB - The deposited, porous layer of the oxide film adjacent to the bulk coolant is expected to have an impact on the activity incorporation (mainly by 60Co, which constitutes a major radiation hazard during shutdown maintenance due to its long half-life) into the structural materials of the primary circuit of nuclear power plants. This work aims at describing the steady-state transport of radioactive and other molecular species through the porous film with a mathematical model, and identifying the limiting phases for the rate of activity build-up from high-temperature aqueous solutions. A necessary prerequisite for gaining a lucid insight into the processes taking place in such systems is a reasonable characterization of the electrical atmosphere within the pore fluid, which is bound to greatly affect the transport properties of the soluble constituents therein. A BWR coolant with high-purity water under NWC conditions was selected as a test problem. It is the simplest case available for performing scoping calculations, yet relevant to actual high-temperature systems. A concise outline of a simple conceptualization of this particular transport system along with its mathematical description are given is this report. Preliminary model results are also presented and briefly discussed.

KW - nuclear power plants

KW - BWR type reactors

KW - corrosion

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KW - high temperature

KW - solutions

KW - hematite

KW - adsorption

KW - complexation

KW - transport modelling

M3 - Report

SN - 951-38-5764-6

T3 - VTT Tiedotteita - Meddelanden - Research Notes

BT - Modelling the transport in the porous layer of oxide films formed on material surfaces in nuclear power plants

PB - VTT Technical Research Centre of Finland

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ER -

Lehikoinen J, Olin M. Modelling the transport in the porous layer of oxide films formed on material surfaces in nuclear power plants: A BWR case study. Espoo: VTT Technical Research Centre of Finland, 2000. 34 p. (VTT Tiedotteita - Meddelanden - Research Notes; No. 2062).