Электронный каталог

Статья

Hassan, A.A.
Optimization of the Cold Moderator for the New Pulsed Reactor NEPTUN / A.A.Hassan, M.V.Bulavin, V.V.Afanasyev // Nuclear Engineering and Design [Electronic resource]. – 2023. – Vol.404. – P.112192. – URL: https://doi.org/10.1016/j.nucengdes.2023.112192. – Bibliogr.:p.16-17.

The Frank Laboratory of Neutron Physics (FLNP) at the Joint Institute for Nuclear Research (JINR) has begun designing a new research reactor, NEPTUN, to replace the IBR-2M (pulsed fast reactor - the name in russian) reactor, which is expected to be out of service between 2032 and 2036. The IBR-2 reactor is a third-generation neutron source that started working in 1982 at Dubna, Russian Federation. The IBR-2M reactor was successfully modernized in 2012. The NEPTUN reactor is a fourth-generation neutron source that will use Np-237 as a nuclear fuel for the first time. It was studied if mesitylene (1,3,5-trimethylbenzene), which is now being utilized effectively in the reactor IBR-2M, might be used as a cold moderator in the new research reactor NEPTUN with an average thermal power of 15 MWt. A study of five materials used as a cold neutron moderator at various temperatures was also conducted. Longer working times for cold moderator material were another goal of optimization. According to the findings, mesitylene at a temperature of 20 K should be used as a cold moderator to get the greatest neutron flux at a wavelength of 3 ≤ λ ≤ 10 Å. Additionally, ortho hydrogen at 20 K could increases the cold neutron flux with wavelengths, λ ˃ 10 Å.



Спец.(статьи,препринты) = С 348 в - Исследовательские ядерные реакторы на тепловых, промежуточных и быстрых нейтронах. Импульсные реакторы
ОИЯИ = ОИЯИ (JINR)2023
Бюллетени = 1/023