With a purpose of identifying the failure mode and associating the ultimate strength of piping components against seismic integrity, many kinds of failure tests have been conducted for thick wall piping for light water reactors (LWRs). However, there are little failure test data on thin wall piping for sodium cooled fast reactors (SFRs). In this paper, a series of failure tests on thin wall elbows for SFRs is presented. Based on the tests, the failure mode of a thin wall piping component under seismic loads was identified to be fatigue. The safety margin included in the current design methodology was clarified quantitatively.

References

References
1.
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.
2.
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.
3.
Suzuki
,
K.
,
Abe
,
H.
, and
Suzuki
,
K.
,
2004
, “
Seismic Proving Test of Ultimate Piping Strength (Ultimate Strength Test)
,”
ASME
Paper No. PVP2004-2954.
4.
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.
5.
Otani
,
A.
,
Nakamura
,
I.
,
Takada
,
H.
, and
Shiratori
,
M.
,
2011
, “
Consideration on Seismic Design Margin of Elbow in Piping
,”
ASME
Paper No. PVP2011-57146.
6.
Nuclear Standards Committee of JEA
,
2008
, “
Technical Code for Seismic Design of Nuclear Power Plants
,” Japan Electric Association, Tokyo, Paper No. JEAC4601-2008 (in Japanese).
7.
Sakai
,
M.
,
Hagiwara
,
Y.
, and
Yamamoto
,
K.
,
1994
, “
Ultimate Strength of Thin-Walled Elbow Under Seismic Loadings
,” Central Research Institute of Electric Power Industry, Tokyo, Report No. U94012 (in Japanese).
8.
Watakabe
,
T.
,
Kitamura
,
S.
,
Tsukimori
,
K.
, and
Morishita
,
M.
,
2013
, “
Study on Ultimate Strength Thin-Wall Piping Components for Fast Breeder Reactors Under Seismic Loading
,”
22nd International Conference on Structural Mechanics in Reactor Technology (SMiRT-22)
, San Francisco, CA, Aug. 18–23, pp.
1575
1584
.
9.
FINAS Ver. 21.0 Manual (in Japanese).
10.
Code for Nuclear Power Generation Facilities
,
2012
, “
Rules on Design and Construction for Nuclear Power Plants
,” Japan Society of Mechanical Engineers, Shinjuku-ku, Japan, Paper No. JSME S NC1-2012 (in Japanese).
11.
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
, Pasadena, CA, Mar. 1–3, pp. 717–719.
12.
Nuclear Safety Bureau,
1984
, “
Seismic Design Standard in Nuclear Facilities for Sodium Cooling Type Fast Breeder Reactor Plants
,”
Nuclear Safety Bureau, Science and Technology Agency
, Chiyoda, Tokyo, Japan, (in Japanese).
13.
Nuclear Safety Bureau,
2004
, “
Technical Standard in Nuclear Facilities for Sodium Cooling Type Fast Breeder Reactor Plants
,”
Nuclear Safety Bureau, Science and Technology Agency
, Chiyoda, Tokyo, Japan, (in Japanese).
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