Published December 1990 | Version v1
Report

Overcooling transient analysis in the frame of MOX fuel management

  • 1. Electricite de France, Villeurbanne (France). Direction des Etudes et Recherches
  • 2. Electricite de France, Villeurbanne (France). Service Etudes et Projets Thermiques et Nucleaires

Description

The resolution to recycle plutonium in french PWR's was an opportunity for EDF to develop its own methodology, for the study of overcooling transients. The aim of this presentation is to describe the present disconnected method between neutronics and thermalhydraulics, used for studying the two transients of main steamline break and inadvertent secondary valve opening (within the design basis overcooling transients). The behaviour of various fuels will be compared through an example of reloading plan for each type: UO2 with 3.25% enrichment and reloading by third; UO2 3.7% by fourth; MOX 30% (UO2 3.25% PUO2 5.30%) by third. (author). 13 figs

Part of:
Recycling of plutonium and uranium in water reactor fuels

Additional details

Publishing Information

Imprint Title
Recycling of plutonium and uranium in water reactor fuels
Imprint Pagination
340 p.
Journal Page Range
p. 321-326.
Report number
IWGFPT--35

Conference

Title
Technical committee meeting on recycling of plutonium and uranium in water reactor fuels.
Dates
13-16 Nov 1989.
Place
Cadarache (France).

Optional Information