First Post Irradiation Examinations on a fast reactor grade MOX fuel (U0.6,Pu0.4)O2 for Pu-burning application, irradiated in the High Flux Reactor

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-03-01 DOI:10.1016/j.jnucmat.2025.155707

S. van Til , A.V. Fedorov , F. Nindiyasari , F. Charpin-Jacobs , G. Uitslag , F. Pasti , E. D'Agata , N. Chauvin

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引用次数: 0

Abstract

To explore fuel operational behaviour and material property evolution under Pu-burning conditions for fast reactor application, several (U,Pu)O₂ MOX fuel pins with increased Pu contents (40 %HM) were irradiated in the HFR Petten in the TRABANT-2 experiment. Fuel pin number 2 (pin 2/2 in short) was designed and produced in the CAPRA programme [1], containing annular (U,Pu)O₂ MOX pellets with a Pu content of 40 % (HM), that were fabricated via classic powder metallurgy, loaded into an austenitic steel cladding tube (15–15Ti). The pin was assembled and immersed in a sodium-filled experimental capsule and irradiated in the High Flux Reactor at a linear heat rate (LHR) of 450–480W/cm and with cladding temperatures not exceeding 600 °C. The irradiation was stopped after three irradiation cycles (74 days) after strong mobility of the central hole was observed in the pellets in neutron radiographs, indicating unexpected high central temperatures.

The post-irradiation neutronics analysis, using neutron fluence detectors located close to the pin confirms a maximum LHR of 447 W/cm. Asymmetric central hole growth and relocation was observed in fuel pin regions exceeding LHR of 407 W/cm.

The temperature history was reconstructed, using instrumentation in the HFR and the sample holder and Post Irradiation Examinations (PIE) on this fuel pin are carried out NRG's Hot Cell Laboratories within the European H2020 project PuMMA [2].

This paper presents a reconstruction of the irradiation history, results of a set of non-destructive examinations (NDE) and fission gas release analysis. The underlying phenomenological explanation on the observed asymmetries is presented and preliminary confirmed by a 2D thermal-mechanical model.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

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.