2005
DOI: 10.1007/s10512-005-0177-7
|View full text |Cite
|
Sign up to set email alerts
|

Application of lead and lead-bismuth in the heat-removal systems of tokamak reactors

Abstract: The salient features of the use of lead and lead-bismuth in the power-generating loops removing heat from the blanket of a tokamak reactor are set forth. The results of experimental and theoretical investigations and analysis in substantiation of the use of heavy liquid-metal coolants in systems converting the energy of a blanket in a tokamak reactor into electricity are presented.One of the main requirements of nuclear power -inherent safety of reactors -is initiating studies of heavy liquidmetal coolants as … Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1

Citation Types

0
1
0

Year Published

2018
2018
2022
2022

Publication Types

Select...
2

Relationship

0
2

Authors

Journals

citations
Cited by 2 publications
(1 citation statement)
references
References 3 publications
0
1
0
Order By: Relevance
“…For instance, uranium dioxide (UO 2 ) is the principal fuel in most significant commercial light-water nuclear power reactors [ 1 , 2 , 3 ]. Moreover, lead is extensively used in fission reactors as a substitute for sodium, and in the blanket of fusion reactors as a substitute for lithium [ 4 ]. Additionally, thorium is used in various nuclear reactors, including light-water, fast spectrum sodium, molten salt, and high-temperature gas-cooled, as well as in fission-fusion hybrid systems and advanced accelerator-driven systems [ 5 , 6 , 7 ].…”
Section: Introductionmentioning
confidence: 99%
“…For instance, uranium dioxide (UO 2 ) is the principal fuel in most significant commercial light-water nuclear power reactors [ 1 , 2 , 3 ]. Moreover, lead is extensively used in fission reactors as a substitute for sodium, and in the blanket of fusion reactors as a substitute for lithium [ 4 ]. Additionally, thorium is used in various nuclear reactors, including light-water, fast spectrum sodium, molten salt, and high-temperature gas-cooled, as well as in fission-fusion hybrid systems and advanced accelerator-driven systems [ 5 , 6 , 7 ].…”
Section: Introductionmentioning
confidence: 99%