0

Full Content is available to subscribers

Subscribe/Learn More  >

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 3 — Preliminary Reactor Safety Analyses Under Depressurization Accidents

[+] Author Affiliations
Masaaki Nakano, Kazutaka Ohashi

Fuji Electric Co., Ltd., Kawasaki, Japan

Koji Okamoto

University of Tokyo, Tokai, Japan

Paper No. ICONE25-66907, pp. V005T05A025; 4 pages
doi:10.1115/ICONE25-66907
From:
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5783-0
  • Copyright © 2017 by ASME

abstract

Preliminary reactor safety analyses were performed for the Pu-burner HTGR (High Temperature Gas-cooled Reactor) to investigate plutonium fuel influence on reactor thermal and kinetic behavior for the depressurization accident which is design base accident, and the depressurization accident without scram, which is beyond design base accident. The analytical results of depressurization accident show that the reactor thermal power is restricted lower than the reference reactor with uranium fuel, because the core width is wider for better Pu-burning performance. The analytical results of depressurization accident without scram show that the re-criticality is delayed compare to the reference reactor with uranium-fueled core, due to its temperature reactivity coefficient. The delay of re-criticality brings that operators have more margins for accident management, for example, manual insertion of shutdown devices to the reactor core.

Copyright © 2017 by ASME

Figures

Tables

Interactive Graphics

Video

Country-Specific Mortality and Growth Failure in Infancy and Yound Children and Association With Material Stature

Use interactive graphics and maps to view and sort country-specific infant and early dhildhood mortality and growth failure data and their association with maternal

NOTE:
Citing articles are presented as examples only. In non-demo SCM6 implementation, integration with CrossRef’s "Cited By" API will populate this tab (http://www.crossref.org/citedby.html).

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In