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Supercritical Water-Cooled Reactors
Author(s) -
Jiejin Cai,
Claude Renault,
Junli Gou
Publication year - 2014
Publication title -
science and technology of nuclear installations
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.417
H-Index - 24
eISSN - 1687-6083
pISSN - 1687-6075
DOI - 10.1155/2014/548672
Subject(s) - supercritical fluid , materials science , nuclear engineering , petroleum engineering , process engineering , environmental science , engineering , thermodynamics , physics
Supercritical water-cooled reactor (SCWR) is the watercooled reactor using supercritical pressure water as coolant [1]. It is considered as one of the promising Generation IV reactors, due to its advantages of plant simplification and high thermal efficiency [2, 3]. Several design concepts of SCWRs have been proposed: (a) supercritical water-cooled thermal neutron reactor; (b) supercritical water-cooled fast neutron reactor; (c) supercritical water-cooled mixed neutron spectrum reactor; (d) supercritical water-cooled pebble bed reactor; (e) supercritical heavy-water-cooled reactor. The detailed design parameters of some typical SCWR concepts around the world are summarized in Table 1 [4]. Recently, the use of thorium in the SCWRs has been investigated [5, 6]. The advantages of the SCWRs are shown as follows [1].

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