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Study of the response of Zircaloy- 4 cladding to thermal shock during water quenching after double sided steam oxidation at elevated temperatures

  • Published:2016-05 Issue: Volume:473 Page:237-248
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Sawarn Tapan K.,Banerjee Suparna,Kumar Sunil

Publisher

Elsevier BV

Subject

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

Reference29 articles.

1. D.O. Hobson, P.L. Rittenhouse, ORNL 4758 (1972).

2. Oxidation of Zircaloy-4 under high temperature steam atmosphere and its effect on ductility of cladding;Kawasaki;J. Nucl. Sci. Technol.,1978

3. A proposed criterion for the oxygen embrittlement of zircaloy-4 fuel cladding;Sawatzky,1979

4. A.M. Garde, T.F Kassner, NUREG/CR-1408 (1980).

5. Zircaloy-4 Cladding Embrittlement due to Inner Surface Oxidation under Simulated Loss-of-Coolant Condition

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2. Revisiting weight-gain correlations for as-fabricated Zircaloy-4 cladding tubes during steam oxidation;Journal of Nuclear Materials;2022-10

3. Experimental study on thermo-chemical behavior of PHWR fuel channel under slumped fuel pin condition;Annals of Nuclear Energy;2021-09

4. High temperature oxidation and room temperature axial strength of pre-oxidized zircaloy-4 cladding after a simulated LOCA;Journal of Nuclear Materials;2021-01

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