1989
DOI: 10.2172/5101359
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The DF-4 fuel damage experiment in ACRR (Annual Core Research Reactor) with a BWR (Boiling Water Reactor) control blade and channel box

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Cited by 6 publications
(3 citation statements)
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“…Fig. 1 Cross-section of DF-4 test section and corresponding BWR core geometry 11) However, because the experimental core section was made on a small scale, further verification was required in order to apply the acquired results to real reactors. use the experimental core section was made rther verification was required in order to esults to real reactors.…”
Section: Effect Of B4c Absorber Materials On Melt Progression and Chemical Forms Of Iodine Or Cesium Under Seve Accident Conditionsmentioning
confidence: 99%
“…Fig. 1 Cross-section of DF-4 test section and corresponding BWR core geometry 11) However, because the experimental core section was made on a small scale, further verification was required in order to apply the acquired results to real reactors. use the experimental core section was made rther verification was required in order to esults to real reactors.…”
Section: Effect Of B4c Absorber Materials On Melt Progression and Chemical Forms Of Iodine Or Cesium Under Seve Accident Conditionsmentioning
confidence: 99%
“…(17) In the SNL-ACRR reactor, the TRAN-series experiments addressed the fuel freezing, where molten fuel generated by nuclear heating was injected by gas pressure into various freezing channels; such as pipes, annular pipes, small pin bundles and flat plates simulating an inter-subassembly gap. (18) The microstructure observation of frozen fuel in out-of-pile experiments suggested interfacial resistance between melt and structure wall due to their discrete contacts. (19) During the cooling process through these contact points, the melt temperature near the wall is cooled below its liquidus temperature and a supercooled layer is formed.…”
Section: Molten Fuel Freezing and Dispersionmentioning
confidence: 99%
“…The melt progression and degradation of fuel bundles in light-water reactors have been studied using research reactors [4][5][6][7]. These experiments showed CONTACT Yuji Ohishi ohishi@see.eng.osaka-u.ac.jp that core component materials chemically interacted with each other to form low-melting-temperature liquid phases in the early stages of bundle degradation.…”
Section: Introductionmentioning
confidence: 99%