Effects of thermal load and cooling condition on weld residual stress in a core shroud with numerical simulation
- 1. Research Group for Nuclear Materials Modeling, Nuclear Science and Energy Directorate, Japan Atomic Engineering Agency (JAEA), Tokai (Japan)
Description
Highlights: ► We simulated weld residual stress in H6a of a core shroud in BWR. ► We studied the effects of thermal load and cooling condition on residual stress. ► We got the suggestions for reducing the weld residual stress by simulations. ► Water cooling at the outside surfaces of the core shroud model was desired. ► Small heat input and slow welding rate were expected. - Abstract: Stress corrosion cracking (SCC) in the heat affected zone is the primary damage form due to weld residual stress, corrosion and neutron irradiation environment in the core shroud of a boiling water reactor. The distribution of weld residual stress around a weld is necessary to be clarified to evaluate the structural integrity of core shroud for SCC. Moreover, studying the effects of welding parameters on residual stress on reducing the residual stress is very important to suppress the initiation and propagation of SCC. In this paper, we used a finite element method (FEM) to clarify the distribution of weld residual stress around the sixth horizontal weld (H6a) between the lower ring and the cylinder in the core shroud. The simulation results of axial stress were consistent with the experimental results at the inside and outside surfaces of the core shroud, respectively. The effects of thermal loads and cooling conditions were also investigated with the same model. We simulated the welding progress with water cooling on the inside and outside surfaces of the core shroud in order to study the influence of cooling conditions on the residual axial stress around the weld. The simulation results indicated that water cooling decreased the residual axial stress at the same side due to changing the temperature-affected fields. Moreover, with fixing the peak temperatures of weld passes, the simulation results of the distribution of residual axial stress by the thermal loads with different heating time were compared. The simulation results suggested that the heating time was expected to be longer and the heat flux to be smaller for reaching the small tension residual axial stress or even compression stress around the H6a weld.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.10.040Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.10.040;
- PII
- S0029-5493(11)00913-7;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 242
- Journal Page Range
- p. 100-107
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43074110
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; COOLING; CYLINDERS; FINITE ELEMENT METHOD; HEAT AFFECTED ZONE; HEAT FLUX; NEUTRON FLUENCE; REACTOR CORES; RESIDUAL STRESSES; SHROUDS; STRESS CORROSION; SURFACES; WATER; WELDED JOINTS; WELDING
- Descriptors DEC
- CALCULATION METHODS; CHEMICAL REACTIONS; COOLING SYSTEMS; CORROSION; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FABRICATION; HYDROGEN COMPOUNDS; JOINING; JOINTS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; STRESSES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZONES
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.