Optimization the thermal moderator for pulsed research reactor NEPTUNE by SERPENT code
https://doi.org/10.56304/S2304487X22020067
Abstract
IBR-2M pulsed reactor has the most intense neutron flux around world ~1016 n/cm2·sec at the moderator surface in the peak. It is expected that, IBR-2M reactor will get out of service between 2030–2032. The decision was taken to construct a new pulsed reactor to replace IBR-2M reactor and complement the research capabilities of the high-flux research nuclear reactor PIK in Russian federation. At the moment, serious work is underway in FLNP JINR at Dubna to design the NEPTUNE reactor. The NEPTUNE reactor is the first reactor in the world to use Np-237 as a nuclear fuel, and it is expected that the neutron flux at the moderator surface (at the peak and average neutron flux) will be the highest in the world. This work aims to optimize the thermal (water) moderator for a new pulsed research reactor NEPTUNE in order to maximize the thermal and epi-thermal neutron flux and to adjust the neutron spectrum. As a result, four possible dimensions were proposed to conduct different experiments. And it was suggested to make a chamber which volume and thickness of water can be changed to adjust the neutron spectrum.
About the Authors
A. A. Hassan
Department of Theoretical and Experimental Physics of Nuclear Reactors, National Research Nuclear University (Moscow Engineering Physics Institute MEPHI); Joint Institute for Nuclear Research JINR
Russian Federation
Russian Federation
115409 Moscow
Dubna, Moscow region, 141980
M. V. Bulavin
Joint Institute for Nuclear Research JINR
Russian Federation
Russian Federation
Dubna, Moscow region, 141980
V. V. Afanasyev
Department of Theoretical and Experimental Physics of Nuclear Reactors, National Research Nuclear University (Moscow Engineering Physics Institute MEPHI)
Russian Federation
Russian Federation
115409 Moscow
M. M. Podlesnyy
Joint Institute for Nuclear Research JINR
Russian Federation
Russian Federation
Dubna, Moscow region, 141980
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Review
For citations:
Hassan A.A., Bulavin M.V., Afanasyev V.V., Podlesnyy M.M. Optimization the thermal moderator for pulsed research reactor NEPTUNE by SERPENT code. Vestnik natsional'nogo issledovatel'skogo yadernogo universiteta "MIFI". 2022;11(2):186–192. https://doi.org/10.56304/S2304487X22020067
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