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"Preliminary calculations for the IBR-4 pulsed reactor. Optimization of the neutron flux", Yu.N. Pepelyshev, A.V. Vinogradov, A.D. Rogov, D. Sumkhuu

Тип события: FLNP SEMINAR
Тип события (для фильтра): Лабораторные семинары

FLNP SEMINAR

05-16-2024 15:00 Conference hall (bldg. 42, 3rd floor)

The IBR-4 pulsed reactor with a power of 4 MW and a pulse repetition rate of 10 s–1 is considered as a pulsed neutron source to replace the IBR-2M reactor, which will be decommissioned by the end of the 2030s. The design of IBR-4 is based on the design of the MBIR multipurpose fast-neutron research reactor with some reconfiguration of the core. The modified core ensures the nuclear safety of the reactor and minimizes low-frequency pulse energy fluctuations inherent in periodic pulsed reactors. The optimal configuration of the IBR-4 core is based on the basic configuration with the addition of beryllium reflectors and small-volume water moderators. The IBR-4 reactor, with a relatively low average power of 4 MW, makes it possible to obtain thermal neutron flux densities on the surface of the water moderator at the level of 1.2∙1014 n/cm2∙s, and in the area close to the surface – 3.0∙1014 n/cm2∙s. Thus, the IBR-4 is a powerful pulsed source of thermal neutrons.

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