Mechanical characterization of superalloys for space reactors
Description
The purpose of this work is the choice of materials usable between 600 and 9000C for nuclear space reactor structures. The main criterion of selection for these materials is their good creep behaviour. Consequently, macroscopic theories of creep and several extrapolation methods were described. Superalloys seem the best materials for the studied range of temperatures. Five of them, base nickel, ones unusual in nuclear industry were selected for their good mechanical properties. Three of them are industrial alloys: the first, HAYNES 230 is a recent one, HASTELLOY S and X are more standard materials. The last two, HASTELLOY XR and PYRAD 38 D are issued from special fabrications. Creep tests metallographic investigations, hardness and tensile tests were performed. A contraction of samples was observed during some creep tests under a low stress, 20MPa at 8000C, for HAYNES 230 and HASTELLOY X. This could be due to a structural evolution of these materials connected to a decrease of the cristalline parameter. In addition, correlations were observed between certain characteristics determined from slow tensile tests and short duration creep tests. These correlations present a large interest because, at the present time, creep tests cannot be executed on irradiated materials in our laboratories. Consequently creep behaviour of irradiated materials seem may be deduced. Further studies are needed to explain and confirm the behaviour of the most interesting materials under low stresses: HAYNES 230 and HASTELLOY XR to anticipate their behaviour in working conditions
Availability note (English)
MF available from INIS under the Report Number.Abstract (French)
Ce travail a pour objet la selection de materiaux de structures utilisables entre 600 et 9000C dans un generateur electronucleaire spatial refroidi au gaz. Le critere essentiel de choix de ces materiaux est leur bonne resistance au fluage. Ceci nous conduit a rappeler les notions des theories macroscopiques du fluage et les methodes essentielles d'extrapolation. Les superalliages sont les materiaux les mieux adaptes a la gamme de temperature envisagee. Cinq d'entre eux, a base nickel, peu utilises jusqu'alors dans l'industrie nucleaire, ont ete choisis pour leurs bonnes proprietes mecaniques. Trois d'entre eux sont des alliages industriels: le premier, l'HAYNES 230 est un materiau recent, les HASTELLOYS S et X sont des materiaux plus classiques. Les deux derniers, l'HASTELLOY XR et le PYRAD 38D correspondent a des fabrications speciales. Des essais de fluage, des examens metallographiques, des essais de durete et de traction ont ete effectues. Une contraction des echantillons a ete mise en evidence durant certains essais de fluage sous faible contrainte, 20 MPa a 8000C, sur l'HAYNES 230 et l'HASTELLOY X. Celle-ci semble liee a l'evolution structurale de ces materiaux qui se traduit, entre autres, par une diminution du parametre cristallin. Des correlations ont pu etre effectuees entre les caracteristiques determinees, respectivement lors d'essais de traction lents et d'essais de fluage de courte duree. Ceci devrait permettre d'estimer le comportement en fluage des materiaux irradies, sur lesquels on ne peut effectuer que des essais de traction. Des etudes devront se poursuivre pour interpreter et verifier le comportement sous faible charge des materiaux les plus prometteurs: l'HAYNES 230 et l'HASTELLOY XR, afin de mieux prevoir les lois de comportement en conditions d'utilisationFiles
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Additional details
Additional titles
- Original title (French)
- Caracterisation mecanique de superalliages pour reacteurs spatiaux
Publishing Information
- Imprint Pagination
- 168 p.
- Report number
- CEA-R--5495
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 21005333
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ALLOY-NI49CR22FE18MO9; ALLOY-NI50CR22FE18MO9; ALLOY-NI62CR16MO15FE3; CREEP; EXPERIMENTAL DATA; EXTRAPOLATION; GRAIN SIZE; HAYNES ALLOYS; HELIUM COOLED REACTORS; HIGH TEMPERATURE; REACTOR MATERIALS; SPACE POWER REACTORS; TENSILE PROPERTIES; VERY HIGH TEMPERATURE; VICKERS HARDNESS
- Descriptors DEC
- ALLOYS; ALUMINIUM ADDITIONS; BORON ADDITIONS; CHROMIUM ALLOYS; COBALT ADDITIONS; COBALT ALLOYS; COBALT BASE ALLOYS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DATA; GAS COOLED REACTORS; HASTELLOYS; HEAT RESISTING ALLOYS; INFORMATION; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; MICROSTRUCTURE; MOBILE REACTORS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NUMERICAL DATA; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; SIZE; TUNGSTEN ADDITIONS; VANADIUM ADDITIONS