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Film boiling behavior of a pressurized water reactor type fuel bundle

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5336723
; ;
An in-pile power-cooling-mismatch (PCM) test designed to investigate the behavior of a nine-rod PWR-type fuel bundle under intermittent and sustained periods of high temperature film boiling operation was recently conducted. Emphasis was placed on departure from nucleate boiling (DNB) and return to nucleate boiling (RNB), rod-to-rod interactions, and fuel rod failure. 23 refs.
Research Organization:
Edgerton, Germeshausen and Grier Inc, Idaho Falls, Idaho, USA
OSTI ID:
5336723
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 52:1; ISSN NUTYB
Country of Publication:
United States
Language:
English

Similar Records

In-pile post-DNB behavior of a nine-rod PWR-type fuel bundle
Conference · Mon Dec 31 23:00:00 EST 1979 · OSTI ID:5595584
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Technical Report · Wed Aug 01 00:00:00 EDT 1979 · OSTI ID:5982504
Fuel rod failure as a consequence of departure from nucleate boiling or dryout. [PWR; BWR]
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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
MECHANICS
NUCLEATE BOILING
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS