Prediction of residual stresses induced by TIG welding of a martensitic steel (X10CrMoVNb9-1)
Description
Within the frame of the development of very high temperature nuclear reactors (VHTR) with gas as heat transfer fluid, some technological challenges are to be faced because of these high temperatures, notably the selection of the material used for the reactor vessel and its welding process. This research thesis aims at developing and validating numerical tools and behaviour models for the thermal-metallurgical-mechanical simulation of the multi-pass TIG welding process. The first part describes the development of simple welding tests (Disk-Spot and Disk-Cycle), the use of temperature and displacement measurement during these tests, and deep residual stress measurements, as well as the identification of the thermal limit conditions for the Disk-Spot test. It then discusses the choice and the identification of the thermal-metallurgical-mechanical behaviour model, with a particular attention to phase transformations and to their coupling with thermal and mechanical aspects. Experimental and simulation results are compared, notably in terms of residual stresses. The numerical implementation of the behaviour model and its integration into the CAST3M finite element software are also described
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Additional details
Additional titles
- Original title (French)
- Prevision des contraintes residuelles induites par le soudage TIG d'un acier martensitique (X10CrMoVNb9-1)
Identifiers
Publishing Information
- Imprint Pagination
- 369 p.
- Report number
- FRCEA-TH--1260
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 42013886
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- C CODES; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; GAS TUNGSTEN-ARC WELDING; MARTENSITIC STEELS; MECHANICAL PROPERTIES; MECHANICAL TESTS; METALLURGICAL EFFECTS; NUCLEAR POWER PLANTS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTOR VESSELS; RESIDUAL STRESSES; THERMODYNAMIC PROPERTIES; VHTR REACTOR
- Descriptors DEC
- ALLOYS; ARC WELDING; CARBON ADDITIONS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; EVALUATION; EXPERIMENTAL REACTORS; FABRICATION; GAS COOLED REACTORS; GAS METAL-ARC WELDING; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; MATERIALS; MATERIALS TESTING; NUCLEAR FACILITIES; PHYSICAL PROPERTIES; POWER PLANTS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; STEELS; STRESSES; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WELDING
Optional Information
- Notes
- This record replaces 41037686 ; Full text also available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS-NKM website for current contact and E-mail addresses: http://www.iaea.org//inis/Contacts/index.htm .Also available from Laboratoire de Mecanique et Technologie, ENS de Cachan / CNRS (UMR 8535) / Universite Paris 6, 61 avenue du President Wilson, F-94235 CACHAN CEDEX (France)