Structural integrity investigation for RPV with various cooling water levels under pressurized melting pool
-
Published:2018-03-02
Issue:1
Volume:9
Page:147-160
-
ISSN:2191-916X
-
Container-title:Mechanical Sciences
-
language:en
-
Short-container-title:Mech. Sci.
Author:
Mao Jianfeng,Liu Yunkai,Bao Shiyi,Luo Lijia,Lu Zhiming,Gao Zengliang
Abstract
Abstract. The strategy denoted as “in-vessel retention (IVR)” is widely used
in severe accident (SA) management by most advanced nuclear power
plants. The essence of IVR mitigation is to provide long-term
external water cooling in maintaining the reactor pressure vessel
(RPV) integrity. Actually, the traditional IVR concept assumed that
RPV was fully submerged into the water flooding, and the melting
pool was depressurized during the SA. The above assumptions weren't
seriously challenged until the occurrence of Fukushima accident on
2011, suggesting the structural behavior had not been appropriately
assessed. Therefore, the paper tries to address the
structure-related issue on determining whether RPV safety can be
maintained or not with the effect of various water levels and
internal pressures created from core meltdown accident. In achieving
it, the RPV structural behaviors are numerically investigated in
terms of several field parameters, such as temperature, deformation,
stress, plastic strain, creep strain, and total damage. Due to the
presence of high temperature melt on the inside and water cooling on
the outside, the RPV failure is governed by the failure mechanisms
of creep, thermal-plasticity and plasticity. The creep and plastic
damages are interacted with each other, which further accelerate the
failure process. Through detailed investigation, it is found that
the internal pressure as well as water levels plays an important
role in determining the RPV failure time, mode and site.
Funder
National Natural Science Foundation of China
Publisher
Copernicus GmbH
Subject
Industrial and Manufacturing Engineering,Fluid Flow and Transfer Processes,Mechanical Engineering,Mechanics of Materials,Civil and Structural Engineering,Control and Systems Engineering
Reference25 articles.
1. Adroguer, B., Chatelard, P., and Van Dorsselaere, J. P.: Core loss during
a severe accident (COLOSS), Nucl. Eng. Des., 221, 55–76, 2003. 2. An, S. M., Song, J. H., Kim, J. Y., Kim, H. Y., and Masanori, N.:
Experimental investigation on molten pool representing corium composition at
Fukushima Daiichi nuclear power plant, J. Nucl. Mater., 478, 164–171, 2016. 3. Buck, M., Burger, M., Godin-Jacqmin, L., Tran, C. T., and Chudanov, V.: The
LIVE program – results of test L1 and joint analyses on transient molten
pool thermal hydraulics, Prog. Nucl. Energ., 52, 46–60, 2010. 4. Duijvestijn, G. and Birchley, J.: Core melt down and vessel failure:
a coupled problem, Nucl. Eng. Des., 191, 17–30, 1999. 5. Gaus-Liu, X., Miassoedov, A., Cron, T., and Wenz, T.: In-vessel melt pool
coolability test-Description and results of LIVE experiments, Nucl. Eng.
Des., 240, 3898–3903, 2010.
Cited by
2 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
|
|