Published December 2002 | Version v1
Report Open

Safety analysis of MOX fuels by fuel performance code

Creators

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

Description

Performance of plutonium rick mixed oxide fuels specified for the Reduced-Moderation Water Reactor (RMWR) has been analysed by modified fuel performance code. Thermodynamic properties of these fuels up to 120 GWd/t burnup have not been measured and estimated using existing uranium fuel models. Fission product release, pressure rise inside fuel rods and mechanical loads of fuel cans due to internal pressure have been preliminarily assessed based on assumed axial power distribution history, which show the integrity of fuel performance. Detailed evaluation of fuel-cladding interactions due to thermal expansion or swelling of fuel pellets due to high burnup will be required for safety analysis of mixed oxide fuels. Thermal conductivity and swelling of plutonium rich mixed oxide fuels shall be taken into consideration. (T. Tanaka)

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Part of:
Summary of the 5th workshop on the reduced moderation water reactor

Additional details

Publishing Information

Imprint Title
Summary of the 5th workshop on the reduced moderation water reactor
Imprint Pagination
218 p.
Journal Page Range
p. 33-46, 129-136
Report number
JAERI-Conf--2002-012

Conference

Title
5. workshop on the reduced moderation water reactor
Dates
8 Mar 2002
Place
Tokai, Ibaraki (Japan)

Optional Information

Notes
8 refs., 13 figs.; This record replaces 34059515