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HT9 swelling in high burnup fast reactor fuel pin components

  • Published:2019-06 Issue: Volume:519 Page:205-216
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Porter D.L.ORCID,Miller B.D.ORCID,Hilton B.A.,Jones M.M.ORCID

Funder

Materials Management and Minimization Program

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference31 articles.

1. Alloy Development for Irradiation Performance, Period Ending September 30, 1983;Gelles,1983

2. Microstructural examination of several commercial ferritic alloys irradiated to high fluence;Gelles;J. Nucl. Mater.,1981

3. Nonswelling Behavior of HT9 Alloy Irradiated to High Exposure;Pitner,1993

4. Alloy Development for Irradiation Performance, Period Ending September 30, 1983;Vitek,1984

5. Alloy Development for Irradiation Performance, Period Ending March 31, 1985;Gelles,1985

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