ENIGMA – Thermo-Mechanical Fuel Performance Code Joins CMS Suite

The United Kingdom’s National Nuclear Laboratory (NNL) and Studsvik Scandpower, Inc. have concluded agreements which appoint Studsvik Scandpower as agent for the sale and distribution of the ENIGMA fuel performance software.

The ENIGMA code is a state-of-the-art fuel performance code, which has been extensively validated and offers customers a comprehensive modeling capability across a range of fuel types.

Studsvik and NNL have worked together in coupling CMS and ENIGMA to provide detailed pin-power histories from CMS into ENIGMA for thermo-mechanical fuel performance assessment, including quantities like:

  • Rod internal pressure
  • Clad stress and strain
  • Rod growth
  • Clad fatigue and ratcheting
  • Pellet-clad mechanical interaction (PCMI)

ENIGMA calculates the thermo-mechanical performance of a LWR fuel rod in both steady-state and transient conditions. UO2, mixed oxide (MOX), Inert Matrix (Yttria Stabilized Zirconia), and (U,Gd)O2 fuel types, as well as Zircaloy-2, Zircaloy-4, ZIRLO, and a range of proprietary low-corrosion alloys, can be modeled. ENIGMA incorporates the models necessary for LWR fuel performance analysis under normal and “off-normal” conditions.

Using detailed pin-power histories from CMS, ENIGMA models such principle processes and properties as:

  • Fuel thermal expansion and conductivity
  • Transient thermal behavior
  • Fuel irradiation, linear and power law creep
  • Sintering of porosity
  • Inexorable solid fission product swelling
  • Fuel grain growth
  • Exposure-dependent radial power variation
  • Fuel axial extrusion
  • Clad thermal expansion and conductivity
  • Clad primary and secondary creep
  • Clad instantaneous plasticity
  • Clad axial growth
  • Clad external oxidation
  • Fuel pellet wheat-sheafing
  • Stress concentration over fuel cracks
  • Stable fission gas release and swelling
  • I-131 release
  • Fuel-clad gap conductance
  • Cladding fatigue
  • Coolant conductivity, specific heat, and viscosity

ENIGMA has been validated against a large database of LWR rod irradiations including test reactor data (e.g. Halden, Riso, Studsvik, BR3, and others) and commercial data; in total, over 500 rod irradiations with exposures to 60 MWd/kgHM (and limited data to 80 GWD/T).

Studsvik will continue to develop ENIGMA along with collaboration from NNL.

For further information, please view the technical resource section or contact us.

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