Home / Publications / Journals / Nuclear Technology / Volume 93 / Number 2
Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 138-146
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34500
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To obtain better simulation results for a Canada deuterium uranium (CANDU) reactor operation, a new simulation method is developed that uses actual detector readings as a correction factor. Detector readings from a CANDU reactor are used to correct the calculated flux distribution during core calculation iterations. A suitable function is found to describe the relationship between the detector flux and the fluxes of mesh points around the detector. The new simulation method is tested by performing numerical calculations for the Wolsung reactor (a CANDU-600). The results show that the new method predicts the core state more accurately with fewer iterations.