Montreal Nuclear Services

Affordable Nuclear Expertise

Reactor Models for Gentilly-2 NPP

GENTILLY-2

SCOPE

Develop reactor physics model of Gentilly-2 for use in safety analyses.

DESCRIPTION

In order to comply with regulatory requirements from the Canadian Nuclear Safety Commission (CNSC), Hydro-Québec needed to update their reactor model to full 2-group models to be used in detailed safety analyses, performed in support to refurbishment. The Gentilly-2 physics model evolved since 1982 to an SCM model, using WIMS-AECL 2 group properties.  However a large number of properties, mostly for structural material, were still based on commissioning models.  The work consisted of identifying dimensions andisotopic compositions of all structural materials and reactivity devices, to model them in 3D within DRAGON, and to integrate them into RFSP core model.  In total, eight core models have been developed to represent the reactor life time (fresh core, plutonium peak core, uncrept time-average core and 20-year crept time-average core), and the adjuster rod design (stainless steel or cobalt adjusters).  The objectives of the work were also to determine the reactivity coefficients for fuel temperature, coolant density and coolant temperature to be used in thermohydraulics code for safety analyses (e.g. CATHENA).


The work was contracted by Hydro-Québec to AECL (Atomic Energy of Canada Ltd).  Dr. Elisabeth Varin was the technical lead and she supervised work performed in Montréal and in Mississauga.


NOTE:  This work was performed / lead by MNS personnel during their previous employment


OUTCOME

  • DRAGON models for cobalt adjuster rods (one to four Cobalt pins), and for structural materials,

  • RFSP core model for fresh core, including depleted bundles, RFSP core model for crept time-average conditions, including 35 crept fuel models

  • Model report including description of all structural material and reactivity mechanisms, creep information after 20 years, SCM fuel table description for uncrept, crept and fresh fuel bundles (natural and depleted uranium composition), RFSP models showing channel power distributions, and kinetics parameters for each core model

  • Reactivity coefficients for each core model for fuel temperature, coolant density and coolant temperature to be used in trip coverage analysis

DISCIPLINES

  • Incremental Cross-sections
  • SCM Fuel Model
  • Neutronics
  • Kinetics Information


CLIENT

Hydro-Québec

Gentilly-2, Canada


Timeframe

2008-2012


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