Article | REF: BN3170 V1

Sodium-cooled fast reactors

Author: Jean-Paul CRETTÉ

Publication date: July 10, 2005

You do not have access to this resource.
Click here to request your free trial access!

Already subscribed? Log in!


Français

3. Technology description

3.1 Integrated or loop primary circuit

Figure 2 shows a schematic diagram of a fast-neutron power plant using sodium as coolant.

To prevent an incident in the steam generator from involving active sodium, a secondary sodium circuit transfers power from the primary circuit to the water-steam circuit.

The primary circuit can be arranged in two main groups:

  • integrated primary circuit (as shown in figure

You do not have access to this resource.

Exclusive to subscribers. 97% yet to be discovered!

You do not have access to this resource.
Click here to request your free trial access!

Already subscribed? Log in!


The Ultimate Scientific and Technical Reference

A Comprehensive Knowledge Base, with over 1,200 authors and 100 scientific advisors
+ More than 10,000 articles and 1,000 how-to sheets, over 800 new or updated articles every year
From design to prototyping, right through to industrialization, the reference for securing the development of your industrial projects

This article is included in

Nuclear engineering

This offer includes:

Knowledge Base

Updated and enriched with articles validated by our scientific committees

Services

A set of exclusive tools to complement the resources

Practical Path

Operational and didactic, to guarantee the acquisition of transversal skills

Doc & Quiz

Interactive articles with quizzes, for constructive reading

Subscribe now!

Ongoing reading
Technology description