Progress in thermohydraulic analysis of accident scenarios of a water-cooled fusion DEMO reactor

M. Nakamura, K. Watanabe, K. Tobita, Y. Someya, H. Tanigawa, H. Utoh, Y. Sakamoto, T. Kunugi, T. Yokomine, T. Araki, S. Asano, K. Asano, W. Gulden

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Abstract

Thermohydraulic analysis of postulated accidents will identify systems responses to accident scenarios and aid to develop design of safety systems and strategies to prevent and mitigate accident propagation. This paper reports recent progress in analysis of some accident scenarios of a water-cooled fusion DEMO reactor. Four types of accidents are particularly considered: ex-vessel loss-of-coolant of the primary cooling system, in-vessel loss-of-coolant of the first wall cooling pipes, loss-of-coolant in blanket modules and loss-of-vacuum. The analysis has identified responses of the DEMO systems to these accidents, pressure loads to confinement barriers for radioactive materials and radiological consequences. Effectiveness of the safety systems and integrity of the confinement barriers against the accidents are discussed.

Original languageEnglish
Title of host publication2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015
PublisherInstitute of Electrical and Electronics Engineers Inc.
ISBN (Electronic)9781479982646
DOIs
Publication statusPublished - 2016 May 31
Externally publishedYes
Event26th IEEE Symposium on Fusion Engineering, SOFE 2015 - Austin, United States
Duration: 2015 May 312015 Jun 4

Publication series

NameProceedings - Symposium on Fusion Engineering
Volume2016-May

Conference

Conference26th IEEE Symposium on Fusion Engineering, SOFE 2015
CountryUnited States
CityAustin
Period15/5/3115/6/4

Keywords

  • Fusion DEMO
  • Safety
  • Thermohydraulics
  • accident analysis

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Fingerprint Dive into the research topics of 'Progress in thermohydraulic analysis of accident scenarios of a water-cooled fusion DEMO reactor'. Together they form a unique fingerprint.

Cite this