Investigation on multilayer failure mechanism of RPV with a high temperature gradient from core meltdown scenario
- 1. Engineering Research Center of Process Equipment and Remanufacturing, Ministry of Education (China)
- 2. Institute of Process Equipment and Control Engineering, Zhejiang University of Technology, Hangzhou, Zhejiang 310032 (China)
Description
Highlights: • The multilayer failure mechanism is investigated for RPV under CHF. • Failure time and location of RPV are predicted under various SA scenarios. • The structural behaviors are analyzed in depth for creep and plasticity. • The effect of internal pressure and temperature gradient is considered. • The structural integrity of RPV is secured within the required 72 creep hours. - Abstract: The Fukushima accident shows that in-vessel retention (IVR) of molten core debris has not been appropriately assessed, and a certain pressure (up to 8.0 MPa) still exists inside the reactor pressure vessel (RPV). In the traditional concept of IVR, the pressure is supposed to successfully be released, and the temperature distributed among the wall thickness is assumed to be uniform. However, this concept is seriously challenged by reality of Fukushima accident with regard to the existence of both internal pressure and high temperature gradient. Therefore, in order to make the IVR mitigation strategy succeed, the numerical investigation of the lower head behavior and its failure has been performed for several internal pressures under high temperature gradient. According to some requirements in severe accident (SA) management of RPV, it should be ensured that the IVR mitigation takes effect in preventing the failure of the structure within a period of 72 h. Subsequently, the failure time and location have to be predicted under the critical heat flux (CHF) loading condition for lower head, since the CHF is limit thermal boundary before the melt-through of RPV. In illustrating the so called 'multilayer failure mechanism', the structural behaviors of RPV are analyzed in terms of the stress, creep strain, deformation, damage on selected paths.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.10.005Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.10.005;
- PII
- S0029-5493(16)30369-7;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 310
- Journal Page Range
- p. 39-47
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48062443
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CREEP; CRITICAL HEAT FLUX; DEFORMATION; FAILURES; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; MELTDOWN; MITIGATION; PRESSURE RANGE MEGA PA; PRESSURE VESSELS; REACTOR VESSELS; SEVERE ACCIDENTS; STRESSES; TEMPERATURE GRADIENTS; TEMPERATURE RANGE 0400-1000 K; WALLS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CONTAINERS; HEAT FLUX; MECHANICAL PROPERTIES; PRESSURE RANGE; REACTOR ACCIDENTS; REACTOR SITES; TEMPERATURE RANGE
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.