Skip to main navigation Skip to search Skip to main content

Study on the System Simulation for the Heat Pipe Failure Transient of Heat Pipe Cooled Reactor

  • Chao Tan
  • , Suizheng Qiu
  • , Chenglong Wang
  • , Zeqin Zhang
  • , Zhengquan Xie
  • , Fei Li
  • CNNC Key Laboratory on Nuclear Industry Simulation
  • Xi'an Jiaotong University

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

Heat Pipe cooled Reactor (HPR) has the advantages of compact structure, high power capacity, high reliability, and inherent safety. It is often considered to have no loss of flow or loss of coolant accident during the heat pipe cooled reactor operation, because there is no flowing coolant working across the major equipment (the coolant only evaporates, condenses and transfers inside the heat pipe) and the working pressure is low. However, due to the limitations of the thermo-physical properties of the fluids inside the tube and the structure of the wick, the heat pipe has an inherent working temperature range, and the heat flux at the hot end is likely to change sharply which could result in the failure of the heat pipe. While the heat pipes are closely arranged in the reactor, an abnormal operation of a single heat pipe may lead to the continuous failure of multiple heat pipes around it in a short time. Thus, the impact of such accidents on the operation safety and reactor reliability should be considered in the heat pipe nuclear reactor design and safety analysis. This paper provides a system-level simulation scheme to analyze the possible consequences of such kind of accident in a rectangular heat pipe reactor. In addition, the important indexes safety margin of the reactor during the transient of heat pipe failure is evaluated and calculated.

Original languageEnglish
Title of host publicationProceedings of the 23rd Pacific Basin Nuclear Conference, Volume 2 - PBNC 2022
EditorsChengmin Liu
PublisherSpringer Science and Business Media Deutschland GmbH
Pages947-963
Number of pages17
ISBN (Print)9789811987793
DOIs
StatePublished - 2023
Event23rd Pacific Basin Nuclear Conference, PBNC 2022 - Chengdu, China
Duration: 1 Nov 20224 Nov 2022

Publication series

NameSpringer Proceedings in Physics
Volume284 SPPHY
ISSN (Print)0930-8989
ISSN (Electronic)1867-4941

Conference

Conference23rd Pacific Basin Nuclear Conference, PBNC 2022
Country/TerritoryChina
CityChengdu
Period1/11/224/11/22

Keywords

  • Heat pipe cooled reactor
  • Heat pipe failure accident
  • Safety analysis
  • System level simulation scheme

Fingerprint

Dive into the research topics of 'Study on the System Simulation for the Heat Pipe Failure Transient of Heat Pipe Cooled Reactor'. Together they form a unique fingerprint.

Cite this