Development of RAPID transport calculation with heterogeneous temperature distribution

Donghao He, William J. Walters

Research output: Contribution to journalArticlepeer-review

Abstract

The RAPID hybrid transport code, based on the fission matrix method, has been developed and previously proven successful on BEAVRS benchmark at hot-zero-power condition. In this work, it is extended to the BEAVRS model to include fuel and moderator temperature feedback. The bi-linear fission matrix interpolation technique was applied to several artificial fuel and moderator temperature distributions. For almost all cases, it provides an accurate calculation result with a keff difference smaller than 70 pcm and 2D pin-wise RMS error smaller than 1% compared to Serpent 2 Monte Carlo reference. In order to decrease the number of databases needed, a plane interpolation routine is developed, which de-couples the fuel and moderator temperature. The RAPID calculation with the plane interpolation reports a similar accuracy to that with the bi-linear interpolation. The bi-linear interpolation required 24 database points from Monte Carlo calculations, while the plane interpolation only needed 10. The plane interpolation allows RAPID to prepare fewer databases while preserving a high accuracy.

Original languageEnglish (US)
Article number107685
JournalAnnals of Nuclear Energy
Volume148
DOIs
StatePublished - Dec 1 2020

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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