﻿Heavy liquid metal cooled fast reactors: peculiarities and development status of the major projects

Orlov, A. I.; Gabaraev, B. A.

Publication:
Heavy liquid metal cooled fast reactors: peculiarities and development status of the major projects

creativeworkseries.issn	2452-3038
dc.contributor.author	Orlov, A. I.
dc.contributor.author	Gabaraev, B. A.
dc.date.accessioned	2023-09-07T06:53:21Z
dc.date.available	2023-09-07T06:53:21Z
dc.date.issued	2023
dc.description.abstract	Fast reactors with heavy liquid metal coolant (lead or eutectic bismuth-lead alloy) are one of the most advanced technologies capable to address the accumulated world nuclear energy issues. This innovative power technology is being developed in Russia, the USA, China and the European Union. Russia is the leader since it has focused on this topic for a number of decades. First concrete started to be poured in June 2021 to form the foundation of the Russian BREST-OD-300 lead cooled reactor scheduled to be started up in 2026. Attention is also given to the development status of the Chinese CLEAR reactor series. A large scope of R&D has been undertaken, and large-scale nonnuclear experimental facilities are under construction. International Euro-US consortiums for the development of the ALFRED, PLFR and MYRRHA reactors do not expect any unsolvable technical issues either and are currently formulating requirements to the test facilities and candidate materials and technologies required for further activities.
dc.identifier.citation	Orlov AI, Gabaraev BA (2023) Heavy liquid metal cooled fast reactors: peculiarities and development status of the major projects. Nuclear Energy and Technology 9(1): 1-18. https://doi.org/10.3897/nucet.9.90993
dc.identifier.doi	10.3897/nucet.9.90993
dc.identifier.issn	2452-3038
dc.identifier.uri	https://openrepository.mephi.ru/handle/123456789/186
dc.identifier.uri	https://doi.org/10.3897/nucet.9.90993
dc.publisher	MEPhI
dc.relation.ispartof	Nuclear Energy and Technology
dc.rights	Creative Commons Attribution License (CC BY 4.0)
dc.subject	Fast reactor
dc.subject	Heavy liquid metal coolant
dc.subject	Closed nuclear fuel cycle
dc.title	Heavy liquid metal cooled fast reactors: peculiarities and development status of the major projects
dc.type	journal-article
dspace.entity.type	Publication
oaire.citation.issue	1
oaire.citation.volume	9
relation.isJournalIssueOfPublication	6635ac2b-60c0-4894-866e-0f1f80780df5
relation.isJournalIssueOfPublication.latestForDiscovery	6635ac2b-60c0-4894-866e-0f1f80780df5
relation.isJournalOfPublication	e11ecc6c-1851-485a-af73-18119b4fce7f