Deposition of Iron Oxide on Heated Surfaces in Boiling Water

Asakura, Yamato; Kikuchi, Makoto; Uchida, Shunsuke; Yusa, Hideo

doi:10.13182/nse78-6

Cited by 64 publications

(14 citation statements)

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“…[92]. Similar results were later obtained in a natural circulation loop operating at a pressure of 10 atm.…”

Section: Impact Of Boiling On Rate Of Particulate Foulingsupporting

confidence: 80%

“…degree of sub-cooling decreases, bubble lifetimes decrease and microlayer evaporation is the dominant process, giving rise to disk-shaped deposits. This hypothesis may offer a means to reconcile the apparently divergent conclusions of Wen and Melandres [97] (who investigated bubble formation in a non-flowing system) with those of Asakura et al [92,93] regarding the relative importance of microlayer evaporation and particle-bubble interactions with respect to the mechanism of particle deposition in boiling water.…”

Section: Investigations Of Particle-bubble Interactionsmentioning

confidence: 84%

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Fouling Of Nuclear Steam Generators: Fundamental Studies, Operating Experience and Remedial Measures Using Chemical Additives

Turner

2013

AECL Nuclear Review

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“…[92]. Similar results were later obtained in a natural circulation loop operating at a pressure of 10 atm.…”

Section: Impact Of Boiling On Rate Of Particulate Foulingsupporting

confidence: 80%

Section: Investigations Of Particle-bubble Interactionsmentioning

confidence: 84%

Fouling Of Nuclear Steam Generators: Fundamental Studies, Operating Experience and Remedial Measures Using Chemical Additives

Turner

2013

AECL Nuclear Review

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“…As a result of careful observation of the crud deposition process and analogy to heat transfer models under nuclear boiling, a microlayer evaporation and dry out model has been developed to analyze crud deposition under boiling at BWR fuel surfaces [57].…”

Section: Crud and Ion Deposition On Fuel Surfacementioning

confidence: 99%

Water chemistry technology – one of the key technologies for safe and reliable nuclear power plant operation

Uchida

Katsumura

2013

Journal of Nuclear Science and Technology

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Water chemistry control is one of the key technologies to establish safe and reliable operation of nuclear power plants. Continuous and collaborative efforts of plant manufacturers and plant operator utilities have been focused on optimal water chemistry control, for which, a trio of requirements for water chemistry should be simultaneously satisfied: (1) better reliability of reactor structures and fuel rods; (2) lower occupational exposure and (3) fewer radwaste sources. Various groups in academia have carried out basic research to support the technical bases of water chemistry in plants. The Research Committee on Water Chemistry of the Atomic Energy Society of Japan (AESJ), which has now been reorganized as the Division of Water Chemistry (DWC) of AESJ, has played important roles to promote improvements in water chemistry control, to share knowledge about and experiences with water chemistry control among plant operators and manufacturers and to establish common technological bases for plant water chemistry and then to transfer them to the next generation of plant workers engaged in water chemistry. Furthermore, the DWC has tried and succeeded arranging R&D proposals for further improvement in water chemistry control through roadmap planning. In the paper, major achievements in plant technologies and in basic research studies of water chemistry in Japan are reviewed. The contributions of the DWC to the longterm safe management of the damaged reactors at the Fukushima Daiichi Nuclear Power Plant until their decommissioning are introduced.

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“…The initial flow rate or mass flux must therefore decrease as the flow resistance increases with time due to growth of a deposit that encroaches on the flow channel. The flow rate reduction then continues until two-phase instability occurs [9]. Note that there will probably be some redistribution of pressure losses with t h e over the various components of the flow path (e.g., the downcomer annulus versus the supports), but this is a second-order effect.…”

Section: Area Change Hpmentioning

confidence: 99%

“…Here, instead of the flow area ratio tenn Cc used in Equation 9.10, the support porosity p , , is used. Brup represents the ratio of support flow area to free-span flow area; ) is therefore the ratio of support cross-sectional area to k -s p a n flow are* and is taken to (approximately) quai the h c t i o n of the particles that would be subject to deposition ont0 the top surface of supportBecause sticking is already accounted for, KG and Kc are not subject to limitation by KA, and are therefore treated independently from the classic transport-attachment model.…”

Section: Enhanced Demsition F?om Flow Develovment On Supportmentioning

confidence: 99%