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Journal ArticleDOI

The influence of the crust layer on RPV structural failure under severe accident condition

TLDR
In this paper, a detailed investigation is conducted by using numerical simulation on the two pressure vessel (RPV) with and without crust layer respectively, and the authors assesses the likelihood and potential failure location, time and mode of the lower head (LH) under the loadings of the critical heat flux (CHF) and slight internal pressure.
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This article is published in Nuclear Engineering and Design.The article was published on 2017-05-01. It has received 7 citations till now. The article focuses on the topics: Creep.

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Citations
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Journal ArticleDOI

Investigation on the RPV structural behaviors caused by various cooling water levels under severe accident

TL;DR: In this paper, the authors investigated the structural behavior of the pressure vessel (RPV) under the severe accident (SA) event of core meltdown and found that the structural failure occurs at the site aside around the water level.
Journal ArticleDOI

Microscopic damage mechanism of SA508 Gr3 steel in ultra-high temperature creep

TL;DR: In this paper, the microstructure of different creep stages was examined by scanning electron microscopy and TEM microscopy, and the results showed that the microscopic damage is mainly induced by creep cavities and coarse second-phase particles.
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The Studies on Multiaxial Creep Behavior of Inconel 718 Notched Bar at 700 °C

TL;DR: In this article, the authors studied the multi-axial creep behavior of Inconel 718 alloy at 700°C and found that the influence of notch radius on its creep behavior and damage evolution was studied through experimental and numerical investigation.
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Development of a lumped-parameter code for efficient assessment of in-vessel melt retention strategy of LWRs

TL;DR: In this paper, a transIVR code was developed to estimate transient one-and two-layer melt pool heat transfer with reasonable accuracies, and two-dimensional representation of heat conduction in the pressure vessel wall, facilitating the coupled thermo-mechanical analysis of the reactor pressure vessel under thermal loads.
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The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident

TL;DR: In this paper, the effect of corium crust on the RPV structural behavior was examined under multilayered crust formation conditions with consideration of detailed thermal characteristics, such as high-temperature gradient across the wall thickness.
References
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Journal ArticleDOI

In-vessel coolability and retention of a core melt

TL;DR: In this article, the efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design, and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow for the delineation of the failure boundaries.
Journal ArticleDOI

Characteristics of Corium Debris Bed Generated in Large-Scale Fuel Coolant Interaction Experiments

TL;DR: In this paper, the formation of corium debris as the result of fuel-coolant interaction (energetic or not) has been studied experimentally in the FARO and KROTOS facilities operated at JRC-Ispra between 1991 and 1999.
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Analysis of safety margin of in-vessel retention for AP1000

TL;DR: In this article, a point estimate procedure has been developed for modeling the steady-state endpoint of two core melt configurations: Configuration I and Configuration II, and the results of benchmark calculations of AP600 by IVRASA were consistent with those of the UCSB and INEEL.
Journal ArticleDOI

Experimental evaluation of the water ingression mechanism for corium cooling

TL;DR: In this paper, the authors evaluated the significance of water ingression cooling in the quenching of molten corium and provided an experimental basis for a water- ingression model that can be incorporated into computer codes used to assess accident management strategies.