Oxidation during fuel-coolant interaction: Advances and modeling-Reference-Cited by-同舟云学术

Oxidation during fuel-coolant interaction: Advances and modeling

Published:2019-05 Issue: Volume:346 Page:200-208
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Loisel V.,Zambaux J.-A.,Hadj-Achour M.,Picchi S.,Coindreau O.,Meignen R.

Funder

ICE

FCI

EDF

ANR

University of Lorraine

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference32 articles.

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2. New modelling of the U-O–Zr phase diagram in the hyper-stoichiometric region and consequences for the fuel rod liquefaction in oxidising conditions;Barrachin;J. Nucl. Mater.,2008

3. Thermodynamic assessment of oxygen diffusion in non-stoichiometric UO2±x;Berthinier;J. Nucl. Mater.,2013

4. Film boiling heat transfer around a very high temperature thin wire immersed into water at pressure from 1 to 210 bar: experimental results and analysis;Berthoud;Int. J. Therm. Sci.,2009

5. The high temperature oxidation of zirconium in water. Technical Report WAPD-104;Bostrom,1954

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