An updated core design for the multi-purpose irradiation facility MYRRHA

Author:

Van den Eynde Gert,Malambu Edouard,Stankovskiy Alexey,Fernandez Rafaël,Baeten Peter

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Cited by 29 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. In-pile transient testing of fuel segments with DIN 1.4970 cladding;Journal of Nuclear Materials;2025-01

2. Simulation of the Measured Reactivity Distributions in the Subcritical MYRRHA Reactor;Energies;2024-05-26

3. Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions;Nuclear Engineering and Design;2023-12

4. Neutron-production double-differential cross sections of natPb and 209Bi in proton-induced reactions near 100 MeV;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2023-11

5. Simulation study of gamma-ray spectroscopy on MYRRHA spent fuel located in lead–bismuth eutectic;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2022-07

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