Parametric study of iodine-129 releases from nuclear fuel to fuel-clad gap & primary coolant in PWRs

Author:

Nasir Rubina,Mirza Sikander M.,Mirza Nasir M.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference24 articles.

1. Booth, A.H., 1958. A suggested method for calculating the diffusion of radioactive rare gas fission products from UO2 fuel elements and a discussion of proposed In-Reactor experiments that may be used to test its validity. , AECL-700, Atomic Energy of Canada Limited.

2. Fission product release from nuclear fuel II. Validation of ASTEC/ELSA on analytical and large scale experiments;Brillant;Ann. Nucl. Energy,2013

3. Fission product release from nuclear fuel I. Physical modelling in the ASTEC code;Brillant;Ann. Nucl. Energy,2013

4. General solution of Bateman equations for nuclear transmutations;Cetnar;Ann. Nucl. Energy,2006

5. Sensitivity analysis of fission product concentrations for light water reactor burned fuel;Chiba;J. Nucl. Sci. Technol.,2010

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