Neutronic calculation of fast reactors by the EUCLID/V1 integrated code

Koltashev, D. A.; Stakhanova, A. A.

Publication:
Neutronic calculation of fast reactors by the EUCLID/V1 integrated code

dc.contributor.author	Koltashev, D. A.
dc.contributor.author	Stakhanova, A. A.
dc.date.accessioned	2024-11-29T13:21:55Z
dc.date.available	2024-11-29T13:21:55Z
dc.date.issued	2017
dc.description.abstract	This article considers neutronic calculation of a fast-neutron lead-cooled reactor BREST-OD-300 by the EUCLID/V1 integrated code. The main goal of development and application of integrated codes is a nuclear power plant safety justification. EUCLID/V1 is integrated code designed for coupled neutronics, thermomechanical and thermohydraulic fast reactor calculations under normal and abnormal operating conditions. EUCLID/V1 code is being developed in the Nuclear Safety Institute of the Russian Academy of Sciences. The integrated code has a modular structure and consists of three main modules: thermohydraulic module HYDRA-IBRAE/LM/V1, thermomechanical module BERKUT and neutronic module DN3D. In addition, the integrated code includes databases with fuel, coolant and structural materials properties. Neutronic module DN3D provides full-scale simulation of neutronic processes in fast reactors. Heat sources distribution, control rods movement, reactivity level changes and other processes can be simulated. Neutron transport equation in multigroup diffusion approximation is solved. This paper contains some calculations implemented as a part of EUCLID/V1 code validation. A fast-neutron lead-cooled reactor BREST-OD-300 transient simulation (fuel assembly floating, decompression of passive feedback system channel) and cross-validation with MCU-FR code results are presented in this paper. The calculations demonstrate EUCLID/V1 code application for BREST-OD-300 simulating and safety justification.
dc.identifier.citation	D A Koltashev and A A Stakhanova 2017 J. Phys.: Conf. Ser. 781 012003
dc.identifier.doi	10.1088/1742-6596/781/1/012003
dc.identifier.issn	1742-6588
dc.identifier.issn	1742-6596
dc.identifier.uri	https://iopscience.iop.org/article/10.1088/1742-6596/781/1/012003
dc.identifier.uri	https://openrepository.mephi.ru/handle/123456789/23918
dc.publisher	IOP Publishing Ltd
dc.relation.ispartof	Journal of Physics: Conference Series
dc.title	Neutronic calculation of fast reactors by the EUCLID/V1 integrated code
dc.type	journal-article
dspace.entity.type	Publication
oaire.citation.volume	781