Irradiation response of the IAEA CRP-3 material FFA measured by fracture toughness specimens

Matti Valo; Kim Wallin; Kari Törrönen; Ralf Ahlstrand

Irradiation response of the IAEA CRP-3 material FFA measured by fracture toughness specimens

Matti Valo, Kim Wallin, Kari Törrönen, Ralf Ahlstrand

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

4 Citations (Scopus)

Abstract

The irradiation response of the French forging material FFA offered by International Atomic Energy Agency (IAEA) has been measured. Charpy-5 and precracked specimens of three-point bending (3-PB) geometry for J-Δa curve measurement have been irradiated in the surveillance position of the Loviisa nuclear power plant (NPP) in a flux of 2 x 10¹¹ n/cm²s to a fluence of approximately 2.0 x 10¹⁹ n/cm², E > 1 MeV, at a temperature of 265°C. The irradiation-induced transition temperature shifts measured with Charpy-5 and fracture toughness specimens are correlated by using indexed temperature values. The shape of the brittle fracture transition curves, measured with 3-PB specimen geometry, for irradiated and reference material states are compared using a statistical brittle fracture model. Both the shape of the average curve and the scatter of the measured points are considered. The effect of irradiation on the ductile fracture behavior based on the measured fracture resistance curves (J-Δa) is presented. The 3-PB specimen geometry is used also for measuring the fracture resistance curves.

Original language	English
Title of host publication	Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels
Subtitle of host publication	An International Review
Editors	Lendell E. Steele
Place of Publication	Philadelphia
Publisher	American Society for Testing and Materials ASTM
Pages	238-248
Volume	4
ISBN (Print)	978-0-8031-1478-4
Publication status	Published - 1993
MoE publication type	A4 Article in a conference publication
Event	IAEA Specialists' Meeting on Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels - Balatonfüred, Hungary Duration: 26 Sep 1990 → 28 Sep 1990

Publication series

Series	ASTM Special Technical Publication
Volume	1170
ISSN	0066-0558

Conference

Conference	IAEA Specialists' Meeting on Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels
Country	Hungary
City	Balatonfüred
Period	26/09/90 → 28/09/90

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Valo, M., Wallin, K., Törrönen, K., & Ahlstrand, R. (1993). Irradiation response of the IAEA CRP-3 material FFA measured by fracture toughness specimens. In L. E. Steele (Ed.), Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Vol. 4, pp. 238-248). American Society for Testing and Materials ASTM. ASTM Special Technical Publication, Vol.. 1170

Valo, Matti ; Wallin, Kim ; Törrönen, Kari ; Ahlstrand, Ralf. / Irradiation response of the IAEA CRP-3 material FFA measured by fracture toughness specimens. Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review. editor / Lendell E. Steele. Vol. 4 Philadelphia : American Society for Testing and Materials ASTM, 1993. pp. 238-248 (ASTM Special Technical Publication, Vol. 1170).

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title = "Irradiation response of the IAEA CRP-3 material FFA measured by fracture toughness specimens",

abstract = "The irradiation response of the French forging material FFA offered by International Atomic Energy Agency (IAEA) has been measured. Charpy-5 and precracked specimens of three-point bending (3-PB) geometry for J-Δa curve measurement have been irradiated in the surveillance position of the Loviisa nuclear power plant (NPP) in a flux of 2 x 1011 n/cm²s to a fluence of approximately 2.0 x 1019 n/cm², E > 1 MeV, at a temperature of 265°C. The irradiation-induced transition temperature shifts measured with Charpy-5 and fracture toughness specimens are correlated by using indexed temperature values. The shape of the brittle fracture transition curves, measured with 3-PB specimen geometry, for irradiated and reference material states are compared using a statistical brittle fracture model. Both the shape of the average curve and the scatter of the measured points are considered. The effect of irradiation on the ductile fracture behavior based on the measured fracture resistance curves (J-Δa) is presented. The 3-PB specimen geometry is used also for measuring the fracture resistance curves.",

author = "Matti Valo and Kim Wallin and Kari T{\"o}rr{\"o}nen and Ralf Ahlstrand",

year = "1993",

language = "English",

isbn = "978-0-8031-1478-4",

volume = "4",

series = "ASTM Special Technical Publication",

publisher = "American Society for Testing and Materials ASTM",

pages = "238--248",

editor = "Steele, {Lendell E.}",

booktitle = "Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels",

address = "United States",

note = "IAEA Specialists' Meeting on Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels ; Conference date: 26-09-1990 Through 28-09-1990",

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Valo, M, Wallin, K, Törrönen, K & Ahlstrand, R 1993, Irradiation response of the IAEA CRP-3 material FFA measured by fracture toughness specimens. in LE Steele (ed.), Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review. vol. 4, American Society for Testing and Materials ASTM, Philadelphia, ASTM Special Technical Publication, vol. 1170, pp. 238-248, IAEA Specialists' Meeting on Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels, Balatonfüred, Hungary, 26/09/90.

Irradiation response of the IAEA CRP-3 material FFA measured by fracture toughness specimens. / Valo, Matti; Wallin, Kim; Törrönen, Kari; Ahlstrand, Ralf.

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review. ed. / Lendell E. Steele. Vol. 4 Philadelphia : American Society for Testing and Materials ASTM, 1993. p. 238-248 (ASTM Special Technical Publication, Vol. 1170).

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

TY - GEN

T1 - Irradiation response of the IAEA CRP-3 material FFA measured by fracture toughness specimens

AU - Valo, Matti

AU - Wallin, Kim

AU - Törrönen, Kari

AU - Ahlstrand, Ralf

PY - 1993

Y1 - 1993

N2 - The irradiation response of the French forging material FFA offered by International Atomic Energy Agency (IAEA) has been measured. Charpy-5 and precracked specimens of three-point bending (3-PB) geometry for J-Δa curve measurement have been irradiated in the surveillance position of the Loviisa nuclear power plant (NPP) in a flux of 2 x 1011 n/cm²s to a fluence of approximately 2.0 x 1019 n/cm², E > 1 MeV, at a temperature of 265°C. The irradiation-induced transition temperature shifts measured with Charpy-5 and fracture toughness specimens are correlated by using indexed temperature values. The shape of the brittle fracture transition curves, measured with 3-PB specimen geometry, for irradiated and reference material states are compared using a statistical brittle fracture model. Both the shape of the average curve and the scatter of the measured points are considered. The effect of irradiation on the ductile fracture behavior based on the measured fracture resistance curves (J-Δa) is presented. The 3-PB specimen geometry is used also for measuring the fracture resistance curves.

AB - The irradiation response of the French forging material FFA offered by International Atomic Energy Agency (IAEA) has been measured. Charpy-5 and precracked specimens of three-point bending (3-PB) geometry for J-Δa curve measurement have been irradiated in the surveillance position of the Loviisa nuclear power plant (NPP) in a flux of 2 x 1011 n/cm²s to a fluence of approximately 2.0 x 1019 n/cm², E > 1 MeV, at a temperature of 265°C. The irradiation-induced transition temperature shifts measured with Charpy-5 and fracture toughness specimens are correlated by using indexed temperature values. The shape of the brittle fracture transition curves, measured with 3-PB specimen geometry, for irradiated and reference material states are compared using a statistical brittle fracture model. Both the shape of the average curve and the scatter of the measured points are considered. The effect of irradiation on the ductile fracture behavior based on the measured fracture resistance curves (J-Δa) is presented. The 3-PB specimen geometry is used also for measuring the fracture resistance curves.

M3 - Conference article in proceedings

SN - 978-0-8031-1478-4

VL - 4

T3 - ASTM Special Technical Publication

SP - 238

EP - 248

BT - Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

A2 - Steele, Lendell E.

PB - American Society for Testing and Materials ASTM

CY - Philadelphia

T2 - IAEA Specialists' Meeting on Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Y2 - 26 September 1990 through 28 September 1990

ER -

Valo M, Wallin K, Törrönen K, Ahlstrand R. Irradiation response of the IAEA CRP-3 material FFA measured by fracture toughness specimens. In Steele LE, editor, Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review. Vol. 4. Philadelphia: American Society for Testing and Materials ASTM. 1993. p. 238-248. (ASTM Special Technical Publication, Vol. 1170).