Effect of microstructure on failure behavior of light water reactor coolant piping under severe accident conditions
被引:1
作者:
Harada, Y
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机构:
Japan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, JapanJapan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, Japan
Harada, Y
[1
]
Maruyama, Y
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Japan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, JapanJapan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, Japan
Maruyama, Y
[1
]
Maeda, A
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Japan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, JapanJapan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, Japan
Maeda, A
[1
]
Shibazaki, H
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Japan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, JapanJapan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, Japan
Shibazaki, H
[1
]
Kudo, T
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Japan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, JapanJapan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, Japan
Kudo, T
[1
]
Hidaka, A
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Japan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, JapanJapan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, Japan
Hidaka, A
[1
]
Hashimoto, K
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Japan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, JapanJapan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, Japan
Hashimoto, K
[1
]
Sugimoto, J
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Japan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, JapanJapan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, Japan
Sugimoto, J
[1
]
机构:
[1] Japan Atom Energy Res Inst, Dept Reactor Safety Res, Tokai, Ibaraki 3191195, Japan
light water reactors;
severe accident;
reactor coolant system piping;
stainless steels;
carbon steel;
proof stress;
flow stress;
creep rupture strength;
micro structure;
piping failure;
D O I:
10.1080/18811248.1999.9726282
中图分类号:
TL [原子能技术];
O571 [原子核物理学];
学科分类号:
0827 ;
082701 ;
摘要:
In a severe accident of light water reactors, the reactor coolant system (RCS) piping might be subjected to thermal loads caused by the decay heat of the deposited fission products and the heat transfer from the hot gases, with an internal pressure in some accident sequences. Tests on the RCS piping failure were performed along with high temperature tensile and creep rupture tests including metallography to investigate the failure behavior. The prediction of the 0.2% proof stress by Arrhenius equation is in good agreement with the measured stress above 800 degrees C for served RCS piping materials. The modified Norton's Law for the short term creep rupture model agrees with the experimental values between 800 and 1,150 degrees C for type 316 stainless steel. The microstructural change was discussed with the effect of the very rapid formation and resolution of the precipitation on the strength at high temperature. The result of the piping failure tests which simulated the severe accident conditions, i.e.: in short-term at high-temperature, could support the plastic limit load prediction of the flow stress model using the 0.2% roof stress.