Optimization of the Thermal Moderator for a New Pulsed Reactor NEPTUN.

Autor: Hassan, A. A., Bulavin, M. V., Afanasyev, V. V., Podlesnyy, M. M.
Zdroj: Journal of Surface Investigation: X-Ray, Synchrotron & Neutron Techniques; Apr2023, Vol. 17 Issue 2, p514-517, 4p
Abstrakt: The fast periodic pulsed research reactor IBR-2 started operating in 1982 at the Joint Institute for Nuclear Research in Dubna, Russian Federation. IBR-2M was successfully upgraded and restarted in 2012. The third-generation neutron source reactor IBR-2M has the world's highest neutron flux per pulse. A new neutron source (the NEPTUN reactor) is currently being designed to replace IBR-2M after it is out of service. The NEPTUN reactor is a fourth-generation pulsed neutron source that uses Np-237 as a nuclear fuel for the first time. The optimization of the thermal moderator (water moderator) of the NEPTUN reactor is considered in order to obtain the highest thermal neutron flux on the extracted neutron beam. It is shown that the increase in water thickness leads directly to a shift of faster neutrons towards thermal spectra, but the maximum neutron flux can be obtained only at an optimum thickness. [ABSTRACT FROM AUTHOR]
Databáze: Complementary Index