A concept is presented for a pressurized, water-cooled, pool-type research nuclear reactor IVV-3 under consideration as a replacement capacity for the operating IVV-2M reactor. The expanded experimental capabilities of the IVV-3 reactor, which are associated with an increase in the thermal power and neutron flux density in experimental bodies, will make it possible not only to keep the existing research and production base but also to become in-demand for solving new problems of the nuclear industry. The concept developed for the IVV-3 reactor is based on the principles of continuity of the layout solutions used for the IVV-2M reactor core and operational safety security of water moderated and cooled pool-type research reactors in our country and abroad.

提出了一个概念，用于加压、水冷、池式研究核反应堆 IVV-3，正在考虑作为正在运行的 IVV-2M 反应堆的替代能力。IVV-3反应堆扩大的实验能力，与实验机构中火力和中子通量密度的增加有关，不仅使现有的研究和生产基地得以保持，而且有可能成为需求解决核工业的新问题。为IVV-3反应堆开发的概念是基于IVV-2M反应堆堆芯布局方案的连续性和国内外水慢化冷却池式研究堆运行安全保障的原则。