Graphite as a core material for Generation IV nuclear reactors
Attributed to:
Mechanisms of Retention and Transport of Fission Products in Virgin and Irradiated Nuclear Graphite
funded by
EPSRC
Abstract
No abstract provided
Bibliographic Information
Digital Object Identifier: http://dx.doi.org/10.1016/b978-0-08-100906-2.00014-8
Publication URI: http://dx.doi.org/10.1016/b978-0-08-100906-2.00014-8
Type: Book Chapter
Book Title: Structural Materials for Generation IV Nuclear Reactors (2017)
Page Reference: 495-532