Method development for studies of environmentally assisted cracking (EAC)

Päivi Karjalainen-Roikonen, Pekka Moilanen, Aki Toivonen, Pertti Aaltonen

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

During the use of nuclear reactors the properties of the structural materials change. Variations in the operation environment, such as changes in water chemistry, may enhance the development and growth of flaws. Neutron radiation causes embrittlement for in-core vessel materials. Radiation, together with water chemistry, increases the possibility of stress corrosion cracking in stainless steels and superalloys used in the reactor internal parts. Research on structural materials endeavours to study the ageing mechanisms of materials, and the possibilities and methods of preventing or forecasting the damage caused to structures by ageing. The objective within the subproject "Material degradation due to corrosive environment" of the RATU2 project was to evaluate the factors affecting the changes in material properties due to the environment and stresses, and to assess their interrelationship. The subproject included among others the following tasks: · Development of routine EAC crack growth testing method for small test specimens. · Application of rising displacement testing to study irradiation assisted stress corrosion cracking (IASCC). New simplified techniques for determination of fracture resistance curves in simulated reactor environments. Multi-specimen bellows loading system to provide more experimental EAC data than can be obtained with previous servo hydraulic or mechanical loading systems.
Original languageEnglish
Title of host publicationRATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants
Subtitle of host publicationSynthesis of achievements 1995-1998
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages105-124
ISBN (Electronic)951-38-5264-4
ISBN (Print)951-38-5263-6
Publication statusPublished - 1998
MoE publication typeA4 Article in a conference publication
EventRATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995−1998 - Espoo, Finland
Duration: 7 Dec 19987 Dec 1998

Publication series

NameVTT Symposium
PublisherVTT
Number190
ISSN (Print)0357-9387
ISSN (Electronic)1455-0873

Conference

ConferenceRATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants
CountryFinland
CityEspoo
Period7/12/987/12/98

Fingerprint

Stress corrosion cracking
Aging of materials
Radiation
Bellows
Testing
Embrittlement
Nuclear reactors
Superalloys
Fracture toughness
Water
Crack propagation
Materials properties
Neutrons
Stainless steel
Hydraulics
Irradiation
Degradation
Defects

Cite this

Karjalainen-Roikonen, P., Moilanen, P., Toivonen, A., & Aaltonen, P. (1998). Method development for studies of environmentally assisted cracking (EAC). In RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998 (pp. 105-124). Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 190
Karjalainen-Roikonen, Päivi ; Moilanen, Pekka ; Toivonen, Aki ; Aaltonen, Pertti. / Method development for studies of environmentally assisted cracking (EAC). RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. Espoo : VTT Technical Research Centre of Finland, 1998. pp. 105-124 (VTT Symposium; No. 190).
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abstract = "During the use of nuclear reactors the properties of the structural materials change. Variations in the operation environment, such as changes in water chemistry, may enhance the development and growth of flaws. Neutron radiation causes embrittlement for in-core vessel materials. Radiation, together with water chemistry, increases the possibility of stress corrosion cracking in stainless steels and superalloys used in the reactor internal parts. Research on structural materials endeavours to study the ageing mechanisms of materials, and the possibilities and methods of preventing or forecasting the damage caused to structures by ageing. The objective within the subproject {"}Material degradation due to corrosive environment{"} of the RATU2 project was to evaluate the factors affecting the changes in material properties due to the environment and stresses, and to assess their interrelationship. The subproject included among others the following tasks: · Development of routine EAC crack growth testing method for small test specimens. · Application of rising displacement testing to study irradiation assisted stress corrosion cracking (IASCC). New simplified techniques for determination of fracture resistance curves in simulated reactor environments. Multi-specimen bellows loading system to provide more experimental EAC data than can be obtained with previous servo hydraulic or mechanical loading systems.",
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Karjalainen-Roikonen, P, Moilanen, P, Toivonen, A & Aaltonen, P 1998, Method development for studies of environmentally assisted cracking (EAC). in RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 190, pp. 105-124, RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants, Espoo, Finland, 7/12/98.

Method development for studies of environmentally assisted cracking (EAC). / Karjalainen-Roikonen, Päivi; Moilanen, Pekka; Toivonen, Aki; Aaltonen, Pertti.

RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. Espoo : VTT Technical Research Centre of Finland, 1998. p. 105-124 (VTT Symposium; No. 190).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

TY - GEN

T1 - Method development for studies of environmentally assisted cracking (EAC)

AU - Karjalainen-Roikonen, Päivi

AU - Moilanen, Pekka

AU - Toivonen, Aki

AU - Aaltonen, Pertti

PY - 1998

Y1 - 1998

N2 - During the use of nuclear reactors the properties of the structural materials change. Variations in the operation environment, such as changes in water chemistry, may enhance the development and growth of flaws. Neutron radiation causes embrittlement for in-core vessel materials. Radiation, together with water chemistry, increases the possibility of stress corrosion cracking in stainless steels and superalloys used in the reactor internal parts. Research on structural materials endeavours to study the ageing mechanisms of materials, and the possibilities and methods of preventing or forecasting the damage caused to structures by ageing. The objective within the subproject "Material degradation due to corrosive environment" of the RATU2 project was to evaluate the factors affecting the changes in material properties due to the environment and stresses, and to assess their interrelationship. The subproject included among others the following tasks: · Development of routine EAC crack growth testing method for small test specimens. · Application of rising displacement testing to study irradiation assisted stress corrosion cracking (IASCC). New simplified techniques for determination of fracture resistance curves in simulated reactor environments. Multi-specimen bellows loading system to provide more experimental EAC data than can be obtained with previous servo hydraulic or mechanical loading systems.

AB - During the use of nuclear reactors the properties of the structural materials change. Variations in the operation environment, such as changes in water chemistry, may enhance the development and growth of flaws. Neutron radiation causes embrittlement for in-core vessel materials. Radiation, together with water chemistry, increases the possibility of stress corrosion cracking in stainless steels and superalloys used in the reactor internal parts. Research on structural materials endeavours to study the ageing mechanisms of materials, and the possibilities and methods of preventing or forecasting the damage caused to structures by ageing. The objective within the subproject "Material degradation due to corrosive environment" of the RATU2 project was to evaluate the factors affecting the changes in material properties due to the environment and stresses, and to assess their interrelationship. The subproject included among others the following tasks: · Development of routine EAC crack growth testing method for small test specimens. · Application of rising displacement testing to study irradiation assisted stress corrosion cracking (IASCC). New simplified techniques for determination of fracture resistance curves in simulated reactor environments. Multi-specimen bellows loading system to provide more experimental EAC data than can be obtained with previous servo hydraulic or mechanical loading systems.

M3 - Conference article in proceedings

SN - 951-38-5263-6

T3 - VTT Symposium

SP - 105

EP - 124

BT - RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Karjalainen-Roikonen P, Moilanen P, Toivonen A, Aaltonen P. Method development for studies of environmentally assisted cracking (EAC). In RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. Espoo: VTT Technical Research Centre of Finland. 1998. p. 105-124. (VTT Symposium; No. 190).