Abstract

The fracture toughness in the heat-affected zone (HAZ), which is located under the weld overlay cladding on the inner surface of the reactor pressure vessel (RPV), was evaluated by considering the inhomogeneous microstructures of the HAZ. In this regard, 0.4T-C(T) specimens and miniature C(T) (Mini-C(T)) specimens were manufactured to clarify the effect of the HAZ on fracture toughness. First, the fracture toughness was evaluated using 0.4T-C(T) specimens targeted on microstructural distribution due to the cladding bead location. The reference temperature (To) of HAZ at middle region of cladding bead was 12 °C higher than that at overlap cladding beads. Second, the fracture toughness was evaluated using Mini-C(T) specimens focused on the microstructural difference with distance from the boundary between the cladding and the base metal. The To value of the central position located at 3–7 mm from the boundary between the cladding and the base metal was higher than those of the other positions in HAZ. However, the To values of HAZ for both 0.4T-C(T) and Mini-C(T) specimens were significantly lower than that of the base metal at a quarter thickness by 40–60 °C. Compared with the literature data that indicated fracture toughness at the inner surface without overlay cladding and the base metal at a quarter thickness, this study concluded that the HAZ under the overlay cladding showed no detrimental effect on the conservatism of the structural integrity assessment of RPV steel.

References

1.
JEA
,
2016
, “
Method of Verification Tests of the Fracture Toughness for Nuclear Power Plant Components
,” Japanese Electric Association Code, Paper No. JEAC 4206-2016 (in Japanese).
2.
Susukida
,
H.
,
Sunamoto
,
D.
,
Satoh
,
M.
, and
Funada
,
T.
,
1977
, “
Fracture Toughness of Heavy Section Steels for Nuclear Reactor Pressure Vessel
,”
Trans. Iron Steel Inst. Jpn.
,
17
(
9
), pp.
497
505
. 10.2355/isijinternational1966.17.497
3.
Katsuyama
,
J.
,
Tobita
,
T.
,
Nishiyama
,
Y.
, and
Onizawa
,
K.
,
2012
, “
Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel
,”
ASME J. Pressure Vessel Technol.
,
134
(
3
), p.
031402
.10.1115/1.4005868
4.
Katsuyama
,
J.
,
Nishikawa
,
H.
,
Udagawa
,
M.
,
Nakamura
,
M.
, and
Onizawa
,
K.
,
2013
, “
Assessment of Residual Stress Due to Overlay-Welded Cladding and Structural Integrity of a Reactor Pressure Vessel
,”
ASME J. Pressure Vessel Technol.
,
135
(
5
), p.
051402
.10.1115/1.4024617
5.
Tanguy
,
B.
,
Marini
,
B.
,
Wident
,
P.
,
Todeschini
,
P.
, and
Joly
,
P.
,
2018
, “
RPV Fracture Toughness of Various Metallurgical Zones at Very High Fluences
,”
Fontevraud 9, Contribution of Materials Investigations and Operating Experience to Light Water NPPs' Safety, Performance and Reliability
, https://www.researchgate.net/publication/342353137_RPV_fracture_toughness_of_various_metallurgical_zones_at_very_high_fluences Avignon, France, Sept. 17–20, pp.
1
12
.
6.
JEA
,
2015
, “
Test Method for Determination of Reference Temperature, to, for Ferritic Steels in the Transition Range
,” Japanese Electric Association Code, Paper No. JEAC 4216-2015 (in Japanese).
7.
Yamamoto
,
M.
,
Kimura
,
A.
,
Onizawa
,
K.
,
Yoshimoto
,
K.
,
Ogawa
,
T.
,
Chiba
,
A.
,
Hirano
,
T.
,
Sugihara
,
T.
,
Sugiyama
,
M.
,
Miura
,
N.
, and
Soneda
,
N.
,
2012
, “
A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: First Round Robin Test on Uniform Specimens of Reactor Pressure Vessel Material
,”
ASME
Paper No. PVP2012-78661.10.1115/PVP2012-78661
8.
Yamamoto
,
M.
,
Kimura
,
A.
,
Onizawa
,
K.
,
Yoshimoto
,
K.
,
Ogawa
,
T.
,
Mabuchi
,
Y.
,
Viehrig
,
H. W.
,
Miura
,
N.
, and
Soneda
,
N.
,
2014
, “
A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens-3rd Report: Comparison of To Under Various Selections of Temperature Conditions
,”
ASME
Paper No. PVP2014-28898.10.1115/PVP2014-28898
9.
Tobita
,
T.
,
Nishiyama
,
Y.
,
Ohtsu
,
T.
,
Udagawa
,
M.
,
Katsuyama
,
J.
, and
Onizawa
,
K.
,
2015
, “
Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens
,”
ASME J. Pressure Vessel Technol.
,
137
(
5
), p.
051405
.10.1115/1.4029428
10.
Ha
,
Y.
,
Tobita
,
T.
,
Ohtsu
,
T.
,
Takamizawa
,
H.
, and
Nishiyama
,
Y.
,
2018
, “
Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels
,”
ASME J. Pressure Vessel Technol.
,
140
(
5
), p.
051402
.10.1115/1.4040642
11.
Yamamoto
,
M.
, and
Miura
,
N.
,
2015
, “
Applicability of Miniature C(T) Specimen for the Master Curve Evaluation of RPV Weld Metal
,”
ASME
Paper No. PVP2015-45545
.10.1115/PVP2015-45545
12.
Ha
,
Y.
,
Takamizawa
,
H.
,
Katsuyama
,
J.
,
Hanawa
,
S.
, and
Nishiyama
,
Y.
,
2019
, “
Ion-Induced Irradiation Hardening of the Weld Heat-Affected Zone in Low Alloy Steel
,”
Nucl. Instrum. Methods Phys. Res., Sect. B
,
461
, pp.
276
282
.10.1016/j.nimb.2019.10.018
13.
Wallin
,
K.
,
1984
, “
The Scatter in KIc Results
,”
Eng. Fract. Mech.
,
19
(
6
), pp.
1085
1093
.10.1016/0013-7944(84)90153-X
14.
Sokolov
,
M. A.
, and
Nanstad
,
R. K.
,
2000
, “
Comparison of Irradiation-Induced Shifts of KJc and Charpy Impact Toughness for Reactor Pressure Vessel Steels
,” Oak Ridge National Laboratory, Oak Ridge, TN, Report No. NUREG/CR-6609.
15.
IAEA
,
2001
, “
Reference Manual on the IAEA JRQ Correlation Monitor Steel for Irradiation Damage Studies
,” International Atomic Energy Agency, Vienna, Austria, Technical Document No. IAEA-TECDOC-1230, https://www-pub.iaea.org/MTCD/Publications/PDF/te_1230_prn.pdf
16.
Yamamoto
,
M.
,
2017
, “
The Master Curve Fracture Toughness Evaluation of Irradiated Plate Material JRQ Using Miniature-C(T) Specimens
,”
ASME
Paper No. PVP2017-66085.10.1115/PVP2017-66085
17.
Yamamoto
,
M.
, and
Kobayashi
,
T.
,
2018
, “
Evaluation of Through Wall Fracture Toughness Distribution of IAEA Reference Material JRQ by Mini-C(T) Specimens and the Master Curve Method
,”
ASME
Paper No. PVP2018-84889.10.1115/PVP2018-84889
18.
Yamamoto
,
M.
, and
Nagai
,
M.
,
2019
, “
PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution
,”
ASME
Paper No. PVP2019-93964.10.1115/PVP2019-93964
19.
Yuya
,
H.
,
Yabuuchi
,
K.
, and
Kimura
,
A.
,
2021
, “
Radiation Embrittlement of Clad-HAZ of RPV of a Decommissioned BWR Plant
,”
J. Nucl. Mater.
,
557
, p.
153300
.10.1016/j.jnucmat.2021.153300
You do not currently have access to this content.