An advanced version of the BERKUT-U/V2.1 code intended for modeling the behavior of fuel rods with oxide or nitride fuel in standard and emergency operating regimes of fast reactors with liquid-metal coolant is being developed at the Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAS), as part of the project Next-Generation Codes of Project Proryv (Breakthrough). The present work reports the results of the validation of an advanced version of the code based on post-reactor studies of BN-600 fuel rods (KETVS-1, -6) and BREST-OD-300 fuel rods (ETVS-5) with mixed uranium-plutonium nitride fuel, irradiated in the BN-600 reactor.

中文翻译：

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用混合铀钚氮化物燃料辐照 Bn-600 燃料棒的反应堆后研究的 Berkut 代码验证

俄罗斯核安全研究所正在开发 BERKUT-U/V2.1 代码的高级版本，该代码旨在模拟在使用液态金属冷却剂的快堆标准和应急运行机制中使用氧化物或氮化物燃料的燃料棒的行为科学院 (IBRAE RAS)，作为 Proryv 项目下一代代码（突破）项目的一部分。目前的工作报告了基于 BN-600 燃料棒（KETVS-1、-6）和 BREST-OD-300 燃料棒（ETVS-5）的反应堆后研究的高级版本代码的验证结果在 BN-600 反应堆中辐照的混合铀钚氮化物燃料。