Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins-Reference-Cited by-同舟云学术

Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins

Published:2016-05 Issue: Volume:473 Page:167-177
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Carmack W.J.,Chichester H.M.,Porter D.L.,Wootan D.W.

Publisher

Elsevier BV

Subject

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

Reference15 articles.

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2. In Situ Observation of Axial Irradiation Growth in Liquid-metal Reactor Metal Fuel;Cramer,1989

3. Ethridge, J.L. to Seidel, B.R., 1988. MFF-2 Axial Fuel Growth to Account for Power Decrease. Personal Communication, September 12.

4. Garner, F.A., Toloczko, M.B., 1995. Irradiation creep and swelling of two LMR heats of HT9. Fusion Materials Semiannual Progress Report for the Period Ending March 31, 1995. DOE/ER-0313/18, 169–178.

5. SAFE: a Computer Code for the Steady State and Transient Thermal Analysis of LMR Fuel Elements;Hayes,1993

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