Abstract

It is a key issue to clarify failure mode of piping in nuclear power plants and its safety margin included in the design practice. In this study, a series of dynamic failure tests of a thin wall tee for sodium-cooled fast reactors was conducted. Some discussions related to the thin wall tee are provided on the failure mode under seismic load, dynamic response behavior, accuracy of fatigue prediction by dynamic elastic-plastic analysis, and a safety margin of fatigue evaluation which is included in conventional design rule.

References

1.
Tagart
,
S.
,
Tang
,
Y. K.
,
Guzy
,
D.
, and
Ranganath
,
S.
,
1990
, “
Piping Dynamic Reliability and Code Rule Change Recommendations
,”
Nucl. Eng. Des.
,
123
(
2–3
), pp.
373
385
.10.1016/0029-5493(90)90258-Y
2.
Suzuki
,
K.
,
Namita
,
Y.
,
Abe
,
H.
,
Ichihashi
,
I.
,
Suzuki
,
K.
,
Ishiwata
,
M.
,
Fujiwaka
,
T.
, and
Yokota
,
H.
,
2002
, “
Seismic Proving Test of Ultimate Piping Strength: Current Status of Preliminary Tests-II
,”
ASME
Paper No. ICONE10-22225. 10.1115/ICONE10-22225
3.
Suzuki
,
K.
,
Namita
,
Y.
,
Abe
,
H.
,
Ichihashi
,
I.
,
Suzuki
,
K.
,
Ishiwata
,
M.
,
Fujiwaka
,
T.
, and
Tai
,
K.
,
2002
, “
Seismic Proving Test of Ultimate Piping Strength: Test Results on Piping Component and Simplified Piping System
,”
ASME
Paper No. PVP2002-1403. 10.1115/PVP2002-1403
4.
Suzuki
,
K.
,
Abe
,
H.
, and
Suzuki
,
K.
,
2004
, “
Seismic Proving Test of Ultimate Piping Strength: Ultimate Strength Test
,”
ASME
Paper No. PVP2004-2954. 10.1115/PVP2004-2954
5.
Nakamura
,
I.
,
Otani
,
A.
,
Sato
,
Y.
,
Takada
,
H.
,
Takahashi
,
K.
, and
Shibutani
,
T.
,
2011
, “
Investigation of Seismic Safety Capacity of Aged Piping System: Shaking Table Test on Piping Systems With Wall Thinning by E-Defense
,”
ASME
Paper No. PVP2011-57560. 10.1115/PVP2011-57560
6.
Otani
,
A.
,
Nakamura
,
I.
,
Takada
,
H.
, and
Shiratori
,
M.
,
2011
, “
Consideration on Seismic Design Margin of Elbow in Piping
,”
ASME
Paper No. PVP2011-57146. 10.1115/PVP2011-57146
7.
ASME
,
2021
, “
Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Facility Components
,” ASME, New York, Standard No. ASME BPVC.III.1.NB-2021.
8.
Japan Electric Association
,
2008
, “
Technical Code for Seismic Design of Nuclear Power Plants
,” Japan Electric Association, Tokyo, Japan, Standard No. JEAC4601-2008 (in Japanese).
9.
Morishita
,
M.
,
Otani
,
A.
,
Nakamura
,
I.
,
Watakabe
,
T.
,
Shibutani
,
T.
, and
Shiratori
,
M.
,
2020
, “
A JSME Code Case on Piping Seismic Design Based on Inelastic Response Analysis and Strain-Based Fatigue Criteria
,”
ASME J. Pressure Vessel Technol.
,
142
(
2
), p.
021203
.10.1115/1.4045674
10.
JSME
,
2019
, “
An Alternative Rules on Seismic Design of Seismic S Class Piping by Elastic-Plastic Response Analysis
,” JSME, Tokyo, Japan, Standard No. JSME NC-CC-008 (in Japanese).
11.
Watakabe
,
T.
,
Tsukimori
,
K.
,
Kitamura
,
S.
, and
Morishita
,
M.
,
2016
, “
Ultimate Strength of a Thin Wall Elbow for Sodium Cooled Fast Reactors Under Seismic Loads
,”
ASME J. Pressure Vessel Technol.
,
138
(
2
), p.
021801
.10.1115/1.4031721
12.
Shibata, H., Makiguchi, M., Ito, A., Ichihashi, I., Hirose, J., Kajimura, Y., Niino, T., Hayashi, T., and Chiba, T., 1983, “A Study on Damping Characteristics of Piping Systems in Nuclear Power Plants,” ASME Pressure Vessels Piping Div., 73, pp. 151–178.
13.
JAEA and CTC, 2013, “
FINAS Ver. 21.0 Manual
,” JAEA and CTC, Tokyo, Japan (in Japanese).
14.
Namita
,
Y.
,
Suzuki
,
K.
,
Abe
,
H.
,
Ichihashi
,
I.
,
Shiratori
,
M.
,
Tai
,
K.
,
Iwata
,
K.
, and
Nebu
,
A.
,
2003
, “
Seismic Proving Test of Eroded Piping: Status of Eroded Piping Component and System Test
,”
ASME
Paper No. PVP2003-2097. 10.1115/PVP2003-2097
15.
Nakane
,
M.
,
Kanno
,
S.
, and
Takagi
,
Y.
,
2011
, “
Effect of Cyclic Pre-Strain on Low Cycle Fatigue Life at Middle High Temperature
,”
Trans. Jpn. Soc. Mech. Eng., Ser. A
,
77
(
777
), pp.
694
697
(in Japanese).10.1299/kikaia.77.694
16.
Kanasaki
,
H.
,
Nomura
,
Y.
,
Asada
,
S.
,
Nakamura
,
T.
, and
Tanaka
,
M.
,
2010
, “
Study on Design Fatigue Curve for Austenitic Stainless Steels in Air
,”
M&M Conference of JSME
, Niigata, Japan, pp.
717
719
(in Japanese).
17.
Nuclear Regulation Authority
,
2013
, “
Interpretation of Ministerial Ordinance for Technical Standard of Nuclear Power Reactors at the Stage of Research and Development and Attached Facilities, Appendix1: Technical Standard in Nuclear Facilities for Sodium Cooling Type Fast Breeder Reactor Plants
,” Nuclear Regulation Authority, Tokyo, Japan, Standard No. 1306193 (in Japanese).
18.
JSME
,
2016
, “
Code for Nuclear Power Generation Facilities: Rules on Design and Construction for Nuclear Power Plants
,”
Japan Society of Mechanical Engineers
,
Tokyo, Japan
, Standard No. JSME S NC1-2016 (in Japanese).
You do not currently have access to this content.