Article | REF: BN3741 V1

Graphites and C/C Composites for Generation IV Nuclear Reactors

Authors: Patrick DAVID, Lionel GOSMAIN

Publication date: November 10, 2020, Review date: September 28, 2021

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

Already subscribed? Log in!


Français

3. Behavior under operating conditions

3.1 Graphites

SCROLL TO TOP

3.1.1 Irradiation damage in graphite

Irradiation damage is caused by particle/matter interactions between the high-energy neutron fission flux, in the range 0.1 to 10 MeV with an average of 2 MeV, and the carbon atoms making up the graphite crystal structure. As the binding energy of carbon atoms in the graphitic plane is around 7 eV, the neutron energy is sufficient to displace the carbon atoms from their initial position in the graphite crystal, as well as transferring a significant amount of kinetic...

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

Functional materials - Bio-based materials

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
Behavior under operating conditions