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Assessment of Longer Transport Times between Failed Fuel and Delayed Neutron Detectors

Modelling for Delayed Neutron failed fuel detection systems in CANDU plants to evaluate system performance
Candesco created a computer model to simulate the Delayed Neutron (DN) system used to detect failed fuel in CANDU power plants. The project work included:
 
  • Evaluation of the effect of longer DN transport times from the Primary Heat Transport System (PHTS) to the DN system through the sample lines.
  • Discussion of contributing sources to degradation of the signal discrimination ratio
  • Quantification of the contribution of tramp uranium to the total background activity in the PHTS
Candesco worked with the Royal Military College of Canada to develop a model for the DN system which incorporated the Steady State and Transient Activity Release (STAR) model for release of fission products of failed fuel in the COMSOL environment and solved the coupled differential equations.
 
The model was used to calculate the change in the Discrimination Ratio as a function of increased transport time, tramp uranium, defect size and element linear power.
This model can be applied to an operating reactor to help determine the location of defective fuel bundles.  

About This Solution

Industry Sector

  • Generation

Generation Type

  • Nuclear

Nature of Service

  • Analysis
  • |
  • Consulting

Client Assets

  • Nuclear Fuel

Tags

  • Fuel bundles
  • |
  • Nuclear Fuel
  • |
  • Candesco
  • |
  • CANDU
  • |
  • Primary Heat Transport