TL;DR: The most recent version, ASSERT-PV 3.2, has enhanced phenomenon models for improved predictions of flow distribution, dryout power and CHF location, and post-dryout (PDO) sheath temperature in horizontal CANDU fuel bundles as mentioned in this paper.
TL;DR: In this paper, the authors developed a fuel rod performance analysis code and validated it using the in-reactor test data, and the fuel rod test rods were fabricated and their irradiation test was completed by an international program.
TL;DR: In this paper, a cooperative study has been initiated at Xi'an Jiaotong University (XJTU) with Atomic Energy of Canada Limited (AECL) to develop a subchannel code ATHAS for preliminary analyses of flow and enthalpy distributions and cladding temperatures in CANDU fuel at super-critical water conditions.
TL;DR: In this article, the authors used the ASSERT-PV subchannel code developed by AECL to optimize the dryout power and pressure drop performances of the CANFLEX ®2 fuel bundle.
TL;DR: In this paper, a subchannel analysis for CANDU-SCWR sliding pressure startup is performed to predict the CHF and PDO heat transfer due to their wide application range.