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ASTM Selected Technical Papers
Effects of Radiation on Materials: 15th International Symposium
By
RE Stoller
RE Stoller
1
Oak Ridge National Laboratory
,
Oak Ridge, Tennessee
;
chairman and editor
Search for other works by this author on:
AS Kumar
AS Kumar
2
University of Missouri-Rolla
,
Rolla, Missouri
;
cochairman and editor
Search for other works by this author on:
DS Gelles
DS Gelles
3
Battelle Pacific Northwest Laboratory
,
Richland, Washington
;
cochairman and editor
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ISBN-10:
0-8031-1477-X
ISBN:
978-0-8031-1477-7
No. of Pages:
1339
Publisher:
ASTM International
Publication date:
1992

The irradiation response of the extensively evaluated Japanese pressure vessel plate material, JRQ, offered by IAEA as a correlation monitor material for international use, has been measured. Charpy V-notch and precracked specimens of 3-point-bend (3-PB) geometry for Ja curve measurement have been irradiated in the surveillance position of the Loviisa NPP at a flux of 2 × 1011 neutrons/(cm2 ∙ s) into a fluence of 2.1 × 1019 neutrons/cm2, E > 1 MeV, at a temperature of 265°C.

The irradiation-induced transition temperature shifts measured with Charpy V-notch and fracture mechanics 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 Behavior of Advanced Reactor Pressure Vessels Steels Under Neutron Irradiation
,” Technical Reports Series No. 265,
International Atomic Energy Agency
, Vienna,
1986
.
2.
Wallin
,
K.
,
Valo
,
M.
,
Rintamaa
,
R.
,
Torrdnen
,
K.
, and
Ahlstrand
,
R.
,
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Third Volume)
, ASTM STP 1011,
ASTM
,
Philadelphia
,
1989
, pp. 91–111.
3.
Wallin
,
K.
,
Valo
,
M.
,
Rintamaa
,
R.
,
Torronen
,
K.
, and
Ahlstrand
,
R.
, “
Characteristics of the IAEA Correlation Monitor Material for Surveillance Programmes
,” Research Report 639,
Technical Research Center of Finland
, Espoo, Finland,
1989
.
4.
Manufacturing History and Mechanical Properties of Japanese Materials Provided for the International Atomic Energy Agency
,” CRP subcommittee report,
Atomic Energy Research Committee, Japan Welding Engineering Society
,
10
1986
.
5.
Wallin
,
K.
, PVP, Vol.
170
:
Innovative Approaches to Irradiation Damage, and Fracture Analysis
,
The American Society of Mechanical Engineers, ASME
,
New York
,
1989
, pp. 93–100.
6.
Saario
,
T.
,
Wallin
,
K.
,
Saarelma
,
H.
,
Valkonen
,
A.
, and
Torronen
,
K.
,
Automated Test Methods for Fracture and Fatigue Crack Growth
, ASTM STP 877, Philadelphia,
1985
, pp. 260–268.
7.
Albrecht
,
P.
,
Andrews
,
W. R.
,
Gudas
,
J. P.
,
Joyce
,
J. A.
,
Loss
,
F. J.
,
McCabe
,
D. E.
,
Schmidt
,
D. W.
, and
Van Der Sluys
,
W. A.
,
Journal of Testing and Evaluation
 0090-3973, Vol.
10
, No.
6
,
1982
, pp. 245–251.
8.
Wallin
,
K.
and
Saario
,
T.
, “
Feasibility of Using Charpy-Size Specimens in J-R Curve Testing
,” CSNI principal working group no. 3: Primary circuit integrity meeting,
Paris
, 16–19 April 1985,
Committee on the Safety of Nuclear Installations
,
Paris
.
9.
Wallin
,
K.
and
Valo
,
M.
, “
Q. A. Check of Two J-R Curve Testing Systems Using Charpy V-Notch Size Specimens
,” Technical Research Centre of Finland, Espoo, Metals Laboratory reports,
1991
, to be published.
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