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Thermo-hydraulic transient behavior calculation of once-through steam generator of integrated PWR

  • Heng Xie
  • , Jinling Zhang
  • , Dounan Jia
  • , Guanghui Su
  • , Zhenwan Yu
  • , Suizheng Qiu
  • Xi'an Jiaotong University

Research output: Contribution to journalArticlepeer-review

4 Scopus citations

Abstract

One of the design aspects to improve reactor safety is the integration of the steam generator of pressurized water reactor (PWR) and other components including pressurizer into pressure vessel. By utilizing a movable boundary spatial discretization technique and choosing suitable heat transfer correlation, the physical mathematical model and calculating code to predicate the thermo-hydraulic behavior of once-through steam generator were established. The calculating results are in good agreement with the experimental data.

Original languageEnglish
Pages (from-to)413-418
Number of pages6
JournalHedongli Gongcheng/Nuclear Power Engineering
Volume19
Issue number5
StatePublished - 1998

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