Skip to main navigation Skip to search Skip to main content

Development and verification of system safety analysis code TSACO

  • Nuclear Power Institute of China

Research output: Contribution to journalArticlepeer-review

Abstract

The HE-FUS3 facility was organized to assess the capability of system code in simulating the thermal-hydraulic and dynamic behavior for High Temperature Gas Reactor. The TSACO (Thermal hydraulic and Safety Analysis code) modeled the HE-FUS3 helium facility at the initial steady state and loss of flow accident (LOFA). The calculated temperature distributions in the loop at the initial steady state are compared with the measured temperatures. The flowrate and test section outlet temperature for LOFA are compared. The calculated results at both steady state and LOFA accident are in good consistent with the experimental results. Good agreements of the experimental and computational results proved the rationality and accuracy of the TSACO modeling.

Original languageEnglish
Pages (from-to)4-8
Number of pages5
JournalHedongli Gongcheng/Nuclear Power Engineering
Volume36
DOIs
StatePublished - 15 Dec 2015

Keywords

  • Code verification
  • HE-FUS3 facility
  • System safety analysis

Fingerprint

Dive into the research topics of 'Development and verification of system safety analysis code TSACO'. Together they form a unique fingerprint.

Cite this