{"title":"三点弯曲CW-316试样的堆内应力松弛:实验与模型","authors":"Guillaume Zumpicchiat , Benoit Tanguy , Pierre Gavoille , Valérie Vandenberghe , Julien Vidal","doi":"10.1016/j.jnucmat.2025.155990","DOIUrl":null,"url":null,"abstract":"<div><div>3-point bending in-pile stress relaxation tests of cold-worked 316 stainless steel have been characterised in the mixed-spectrum OSIRIS reactor up to 7 dpa at 330<!--> <!-->°C. Relaxation kinetics were determined based on out of pile interphase measurements. The experimental design allows to study initial prescribed stress levels from 100 MPa up to 600 MPa and to investigate transient (primary) and steady-state (secondary) stress relaxation. Relaxation kinetics were found to be unaffected by initial prescribed stress but to depend on the cold work level of the samples. No incubation dose was observed, even for samples loaded at low initial stresses. Experimental results were interpreted using FE modelling to take into account the non-uniform stress distribution existing in 3-point bending samples loaded in the elasto-plastic domain. The linearly stress-dependent creep law, consisting of two terms representing transient and steady-state creep regimes, allows for a very good description of experimental relaxation kinetics all over the investigated stress range. The primary creep amplitude parameter was found to be dependent on the cold work level, which is consistent with literature. A steady state creep coefficient of 0.96 10<sup>−6</sup> MPa<sup>−1</sup>.dpa<sup>−1</sup> consistent with the values reported from fast reactors was obtained independently on the cold work level. Also it was shown that the stress relaxation ratio can be directly determined based on deflection relaxation ratio despite the non-uniform stress state and residual stresses into the samples.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"616 ","pages":"Article 155990"},"PeriodicalIF":2.8000,"publicationDate":"2025-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"In-reactor stress relaxation of 3-point bending CW-316 samples: Experiments and modelling\",\"authors\":\"Guillaume Zumpicchiat , Benoit Tanguy , Pierre Gavoille , Valérie Vandenberghe , Julien Vidal\",\"doi\":\"10.1016/j.jnucmat.2025.155990\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>3-point bending in-pile stress relaxation tests of cold-worked 316 stainless steel have been characterised in the mixed-spectrum OSIRIS reactor up to 7 dpa at 330<!--> <!-->°C. Relaxation kinetics were determined based on out of pile interphase measurements. The experimental design allows to study initial prescribed stress levels from 100 MPa up to 600 MPa and to investigate transient (primary) and steady-state (secondary) stress relaxation. Relaxation kinetics were found to be unaffected by initial prescribed stress but to depend on the cold work level of the samples. No incubation dose was observed, even for samples loaded at low initial stresses. Experimental results were interpreted using FE modelling to take into account the non-uniform stress distribution existing in 3-point bending samples loaded in the elasto-plastic domain. The linearly stress-dependent creep law, consisting of two terms representing transient and steady-state creep regimes, allows for a very good description of experimental relaxation kinetics all over the investigated stress range. The primary creep amplitude parameter was found to be dependent on the cold work level, which is consistent with literature. A steady state creep coefficient of 0.96 10<sup>−6</sup> MPa<sup>−1</sup>.dpa<sup>−1</sup> consistent with the values reported from fast reactors was obtained independently on the cold work level. Also it was shown that the stress relaxation ratio can be directly determined based on deflection relaxation ratio despite the non-uniform stress state and residual stresses into the samples.</div></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"616 \",\"pages\":\"Article 155990\"},\"PeriodicalIF\":2.8000,\"publicationDate\":\"2025-07-07\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Nuclear Materials\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0022311525003848\",\"RegionNum\":2,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q3\",\"JCRName\":\"MATERIALS SCIENCE, MULTIDISCIPLINARY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525003848","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
In-reactor stress relaxation of 3-point bending CW-316 samples: Experiments and modelling
3-point bending in-pile stress relaxation tests of cold-worked 316 stainless steel have been characterised in the mixed-spectrum OSIRIS reactor up to 7 dpa at 330 °C. Relaxation kinetics were determined based on out of pile interphase measurements. The experimental design allows to study initial prescribed stress levels from 100 MPa up to 600 MPa and to investigate transient (primary) and steady-state (secondary) stress relaxation. Relaxation kinetics were found to be unaffected by initial prescribed stress but to depend on the cold work level of the samples. No incubation dose was observed, even for samples loaded at low initial stresses. Experimental results were interpreted using FE modelling to take into account the non-uniform stress distribution existing in 3-point bending samples loaded in the elasto-plastic domain. The linearly stress-dependent creep law, consisting of two terms representing transient and steady-state creep regimes, allows for a very good description of experimental relaxation kinetics all over the investigated stress range. The primary creep amplitude parameter was found to be dependent on the cold work level, which is consistent with literature. A steady state creep coefficient of 0.96 10−6 MPa−1.dpa−1 consistent with the values reported from fast reactors was obtained independently on the cold work level. Also it was shown that the stress relaxation ratio can be directly determined based on deflection relaxation ratio despite the non-uniform stress state and residual stresses into the samples.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.