Core Thoughts

A moderator to thermalize the neutrons is highly desirable to maximise the probability of fission and transmutation while minimising the inventory of fissile and fertile materials in the reactor. A possible moderator for a molten-salt reactor may be colloidal graphite in molten salt.

Such a 3-fluid reactor would feature a graphite moderator that is unstressed, dynamically tuneable, refreshable and not in contact with either the fuel or the blanket fluids. The void coefficient becomes more sharply negative in a liquid than a solid, improving load response. Heat developed in, and transferred into the moderator is also removable by external heat exchange.

Advertisements
This entry was posted in Energy for Civilisation, Nuclear and tagged . Bookmark the permalink.

Leave a Reply

Fill in your details below or click an icon to log in:

WordPress.com Logo

You are commenting using your WordPress.com account. Log Out / Change )

Twitter picture

You are commenting using your Twitter account. Log Out / Change )

Facebook photo

You are commenting using your Facebook account. Log Out / Change )

Google+ photo

You are commenting using your Google+ account. Log Out / Change )

Connecting to %s