Influence of point defect accumulation on in-pile thermal conductivity degradation: Fuel rod defect distribution and deviation between in-pile and post irradiation thermal conductivity

Author:

Ferrigno JoshuaORCID,Adnan SaqeebORCID,Khafizov MaratORCID

Publisher

Elsevier BV

Subject

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

Reference72 articles.

1. Fuel failure experiences in U.S;Cheng;Light Water Reactors,2003

2. A review of nuclear fuel performance codes;Aybar;Prog. Nucl. Energy,2005

3. MATPRO: Version 09. A Handbook Of Materials Properties For Use In The Analysis Of Light Water Reactor Fuel Rod Behavior,; SEE CODE- 9502158 EG and G Idaho, Inc., Idaho Falls (USA);MacDonald,1976

4. A review of fuel performance modelling;Van Uffelen;J. Nucl. Mater.,2019

5. TRANSURANUS: a fuel rod analysis code ready for use;Lassmann;J. Nucl. Mater.,1992

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