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Loop Studies Addressing the Hydraulic Impact From the Presence of Part-Length Fuel Rods Within a BWR Fuel Element, Using Water and Air-Water Mixtures at Room Temperature and Low Pressure

[+] Author Affiliations
Hamid Sadeghi, Jan Blomstrand

Royal Institute of Technology, Stockholm, Sweden

Guillermo Urrutia

CNEN, Buenos Aires, Argentina

Paper No. ICONE16-48235, pp. 301-308; 8 pages
  • 16th International Conference on Nuclear Engineering
  • Volume 3: Thermal Hydraulics; Instrumentation and Controls
  • Orlando, Florida, USA, May 11–15, 2008
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4816-7 | eISBN: 0-7918-3820-X
  • Copyright © 2008 by ASME


There are a number of reactivity incidents which could possibly occur at low pressure in boiling water reactor (BWR) cores, and some of them may cause local boiling — entailing reactivity feed-back. Unfortunately, theoretical studies of events of this nature are somewhat hampered by the dearth of knowledge about the thermal-hydraulics involved. The research presented here addresses one particular aspect of this issue: how is BWR core thermal-hydraulics — at low pressure — affected in such fuel assemblies where some full-length rods have been replaced by part-length rods?

Copyright © 2008 by ASME



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