Ageing phenomena (AGE)

Ageing and oxidation of reactor materials

Pertti Aaltonen, Petri Kinnunen, Päivi Karjalainen-Roikonen, Timo Laitinen, Lena Hansson, Matti Valo

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Abstract

The target of this project has been to study and model the changing properties of ageing pressure boundary materials used in nuclear power plants. Models to estimate and methods to measure the behaviour of these materials under various operational conditions in nuclear power plants have been developed and applied. In nuclear reactors stainless steels are mainly used as a material facing the primary circuit environment. Thus, the main focus has been to study the role of the primary circuit environment and surface oxide films containing Fe, Ni and Cr on changes occurring in the mechanical properties and degradation susceptibility of ageing pressure boundary materials.
Original languageEnglish
Title of host publicationFINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002
Subtitle of host publicationFinal Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages38-51
ISBN (Electronic)951-38-6086-8
ISBN (Print)951-38-6085-X
Publication statusPublished - 2002
MoE publication typeNot Eligible

Publication series

NameVTT Tiedotteita - Research Notes
PublisherVTT
Number2164
ISSN (Print)1235-0605
ISSN (Electronic)1455-0865

Fingerprint

Aging of materials
Oxidation
Nuclear power plants
Networks (circuits)
Nuclear reactors
Oxide films
Stainless steel
Degradation
Mechanical properties

Cite this

Aaltonen, P., Kinnunen, P., Karjalainen-Roikonen, P., Laitinen, T., Hansson, L., & Valo, M. (2002). Ageing phenomena (AGE): Ageing and oxidation of reactor materials. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report (pp. 38-51). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2164
Aaltonen, Pertti ; Kinnunen, Petri ; Karjalainen-Roikonen, Päivi ; Laitinen, Timo ; Hansson, Lena ; Valo, Matti. / Ageing phenomena (AGE) : Ageing and oxidation of reactor materials. FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. pp. 38-51 (VTT Tiedotteita - Research Notes; No. 2164).
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Aaltonen, P, Kinnunen, P, Karjalainen-Roikonen, P, Laitinen, T, Hansson, L & Valo, M 2002, Ageing phenomena (AGE): Ageing and oxidation of reactor materials. in FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2164, pp. 38-51.

Ageing phenomena (AGE) : Ageing and oxidation of reactor materials. / Aaltonen, Pertti; Kinnunen, Petri; Karjalainen-Roikonen, Päivi; Laitinen, Timo; Hansson, Lena; Valo, Matti.

FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. p. 38-51 (VTT Tiedotteita - Research Notes; No. 2164).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

TY - CHAP

T1 - Ageing phenomena (AGE)

T2 - Ageing and oxidation of reactor materials

AU - Aaltonen, Pertti

AU - Kinnunen, Petri

AU - Karjalainen-Roikonen, Päivi

AU - Laitinen, Timo

AU - Hansson, Lena

AU - Valo, Matti

PY - 2002

Y1 - 2002

N2 - The target of this project has been to study and model the changing properties of ageing pressure boundary materials used in nuclear power plants. Models to estimate and methods to measure the behaviour of these materials under various operational conditions in nuclear power plants have been developed and applied. In nuclear reactors stainless steels are mainly used as a material facing the primary circuit environment. Thus, the main focus has been to study the role of the primary circuit environment and surface oxide films containing Fe, Ni and Cr on changes occurring in the mechanical properties and degradation susceptibility of ageing pressure boundary materials.

AB - The target of this project has been to study and model the changing properties of ageing pressure boundary materials used in nuclear power plants. Models to estimate and methods to measure the behaviour of these materials under various operational conditions in nuclear power plants have been developed and applied. In nuclear reactors stainless steels are mainly used as a material facing the primary circuit environment. Thus, the main focus has been to study the role of the primary circuit environment and surface oxide films containing Fe, Ni and Cr on changes occurring in the mechanical properties and degradation susceptibility of ageing pressure boundary materials.

M3 - Chapter or book article

SN - 951-38-6085-X

T3 - VTT Tiedotteita - Research Notes

SP - 38

EP - 51

BT - FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Aaltonen P, Kinnunen P, Karjalainen-Roikonen P, Laitinen T, Hansson L, Valo M. Ageing phenomena (AGE): Ageing and oxidation of reactor materials. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo: VTT Technical Research Centre of Finland. 2002. p. 38-51. (VTT Tiedotteita - Research Notes; No. 2164).