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ASTM Selected Technical Papers
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume)
By
LE Steele
LE Steele
1
Consulting Professional Nuclear Engineer, Springfield, VA
;
Symposium Chairman and Editor
.
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ISBN-10:
0-8031-1478-8
ISBN:
978-0-8031-1478-4
No. of Pages:
416
Publisher:
ASTM International
Publication date:
1993

The irradiation response of the French forging material FFA offered by International Atomic Energy Agency (IAEA) has been measured. Charpy-V and precracked specimens of three-point bending (3-PB) geometry for Ja curve measurement have been irradiated in the surveillance position of the Loviisa nuclear power plant (NPP) in a flux of 2 × 1011 n/cm2s to a fluence of approximately 2.0 × 1019 n/cm2E > 1 MeV, at a temperature of 265°C.

The irradiation-induced transition temperature shifts measured with Charpy-V and fracture toughness specimens are correlated by using indexed temperature values.

The shapes 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 (Ja) is presented. The 3-PB specimen geometry is used also for measuring the fracture resistance curves.

1.
Analysis of the Behaviour of Advanced Reactor Pressure Vessels Steels Under Neutron Irradiation
,” Technical Reports Series 265,
IAEA
, Vienna,
1986
.
2.
Wallin
,
K.
,
Valo
,
M.
,
Rintamaa
,
R.
,
Törrönen
,
K.
, and
Ahlstrand
,
R.
,
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Third Volume)
, ASTM STP 1011,
American Society for Testing and Materials
,
Philadelphia
,
1989
, pp. 91–111.
3.
Wallin
,
K.
,
Valo
,
M.
,
Rintamaa
,
R.
,
Törrönen
,
K.
, and
Ahlstrand
,
R.
, '
Characteristics of the French Forging Material FFA
” in press.
4.
Wallin
,
K.
,
PVP—Vol. 170, Innovative Approaches to Irradiation Damage and Fracture Analysis
,
American Society of Mechanical Engineers
,
New York
,
1989
, pp. 93–100.
5.
Saario
,
T.
,
Wallin
,
K.
,
Saarelma
,
H.
,
Valkonen
,
A.
, and
Törrönen
,
K.
,
Automated Test Methods for Fracture and Fatigue Crack Growth
, ASTM STP 877,
American Society for Testing and Materials
,
Philadelphia
,
1985
, pp. 260–268.
6.
Wallin
,
K.
and
Saario
,
T.
, “
Feasibility of Using Charpy-Size Specimens in J-R Curve Testing
,”
Proceedings
, Second CSNI Workshop on Ductile Fracture Test Methods,
Loss
F. J.
, Ed., NUREG/CP-0064,
U.S. Nuclear Regulatory Commission
,
Washington, DC
,
1988
, pp. 105–111.
7.
Wallin
,
K.
and
Valo
,
M.
in press.
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