Published 2019 | Version v1
Book

Overview of reactor systems and operational environments for structural materials in Gen-IV fission reactor

  • 1. Alamos Natl Lab, Los Alamos, NM (United States)
  • 2. Argonne Natl Lab, Lemont, IL (United States)
  • 3. Oak Ridge Natl Lab, Oak Ridge, TN (United States)
  • 4. European Commiss, JRC, Petten (Netherlands)
  • 5. CEA Saclay, Gif Sur Yvette (France)

Description

A summary of the operating conditions leading to materials challenges for candidate reactor materials has been provided for the six Gen-IV Reactor concepts. This includes two liquid metal cooled fast reactors (SFR and LFR), two helium cooled reactors (VHTR and GFR), the molten salt cooled reactor (MSR), and the supercritical water cooled reactor (SCWR). The reactor concept with the largest experience base is the SFR although research is underway to further the development of the others. The following chapters provide more detail on development and understanding of improved materials leading to further advancement of these advanced reactor concepts. (authors)

Availability note (English)

Available from doi: http://dx.doi.org/10.1016/b978-0-12-397046-6.00002-2
Part of:
Structural Alloys for Nuclear Energy Application

Additional details

Publishing Information

Publisher
Elsevier Inc.
Imprint Place
Cambridge (United States)
ISBN
978-0-12-397046-6
Imprint Title
Structural Alloys for Nuclear Energy Application
Imprint Pagination
648 p.
Journal Page Range
p. 23-49

Optional Information

Notes
70 refs.