Ex-vessel boiling experiments: laboratory- and reactor-scale testing of the flooded cavity concept for in-vessel core retention Part I: Observation of quenching of downward-facing surfaces

Chu, T. Y.; Bainbridge, B.L.; Simpson, R.B.; Bentz, J.H.

doi:10.1016/s0029-5493(96)01278-2

Cited by 46 publications

(5 citation statements)

References 8 publications

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“…Thus, the Bond number is a ratio of the gap size to the capillary length, and may also be expressed as Chu et al (1997) observed the quenching of either flat or curved downward facing aluminum surfaces with 61 cm diameters to simulate and assess the ex-vessel boiling process for in-vessel core retention. The experimental masses were heated to an elevated temperature between 160 and 330°C, and then plunged into a pool of water at saturation.…”

Section: Introductionmentioning

confidence: 99%

Subcooled pool boiling of water on a downward-facing stainless steel disk in a gap

Su¹,

Wu²,

Sugiyama³

2008

International Journal of Multiphase Flow

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Section: Introductionmentioning

confidence: 99%

Subcooled pool boiling of water on a downward-facing stainless steel disk in a gap

Su¹,

Wu²,

Sugiyama³

2008

International Journal of Multiphase Flow

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“…Most studies clearly reveal that CHF decreases as surface orientation changes from upward-facing horizontal (0 ) to vertical (90 ) to downward-facing horizontal (180 ) [19]- [25]. Recently, the author and co-workers performed photographic studies of pool boiling in dielectric fluids at different surface orientations in order to ascertain the CHF trigger mechanism associated with each orientation [26], [27].…”

Section: Press-on Finsmentioning

confidence: 99%

Assessment of high-heat-flux thermal management schemes

Mudawar¹

ITHERM 2000. The Seventh Intersociety Conference on Thermal and Thermomechanical Phenomena in Electronic Systems (Cat. No.00CH3

193

240

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Abstract-This paper explores the recent research developments in high-heat-flux thermal management. Cooling schemes such as pool boiling, detachable heat sinks, channel flow boiling, microchannel and mini-channel heat sinks, jet-impingement, and sprays, are discussed and compared relative to heat dissipation potential, reliability, and packaging concerns. It is demonstrated that, while different cooling options can be tailored to the specific needs of individual applications, system considerations always play a paramount role in determining the most suitable cooling scheme. It is also shown that extensive fundamental electronic cooling knowledge has been amassed over the past two decades. Yet there is now a growing need for hardware innovations rather than perturbations to those fundamental studies. An example of these innovations is the cooling of military avionics, where research findings from the electronic cooling literature have made possible the development of a new generation of cooling hardware which promise order of magnitude increases in heat dissipation compared to today's cutting edge avionics cooling schemes.

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“…Such high‐temperature gradient coupled with the remaining pressure will pose a serious threat to the structural integrity of RPVs. Previous structural experiments of RPV under the artificial melting‐core accident conditions, such as Lower Head Failure (LHF) 4 and Failure of Reactor Vessel Retention (FOREVER), 5 have shown the creep failure as one of the predominant failure mechanisms endangering the structural integrity of RPVs 6 . Therefore, a thorough understanding of creep mechanisms and behaviors of RPV materials at extremely high temperatures is essential for successful implementation of IVR.…”

Section: Introductionmentioning

confidence: 99%

Creep behavior and life prediction of a reactor pressure vessel steel above phase‐transformation temperature via a deformation mechanism‐based creep model

Wang

Zheng

et al. 2023

Fatigue Fract Eng Mat Struct

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For nuclear power generation as a carbon‐neutral energy source, in‐vessel retention (IVR) must be implemented to maintain the structural integrity of nuclear reactor pressure vessel (RPV) for more than 72 h under severe accidental conditions. This technology requires accurate prediction of creep deformation and life of RPV material being operated under pressure and extremely high‐temperature gradient. The current work develops a simplified deformation‐mechanism‐based true‐stress (DMTS) model for creep behavior/life‐prediction of SA508 Gr.3 steel, a typical RPV material, above the phase transformation temperatures (800–1000°C). This model is used to evaluate the time to specific creep strain (t3% and t5%) and rupture (tr), in comparison with popular empirical methods such as Orr–Sherby–Dorn (OSD) and Larson–Miller (LM). The simplified DMTS model achieves an excellent agreement with the experimental observations. The controlling deformation mechanisms are also discussed by metallurgical examinations, which provide the physical premise for the model development and application.

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Ex-vessel boiling experiments: laboratory- and reactor-scale testing of the flooded cavity concept for in-vessel core retention Part I: Observation of quenching of downward-facing surfaces

Cited by 46 publications

References 8 publications

Subcooled pool boiling of water on a downward-facing stainless steel disk in a gap

Subcooled pool boiling of water on a downward-facing stainless steel disk in a gap

Assessment of high-heat-flux thermal management schemes

Creep behavior and life prediction of a reactor pressure vessel steel above phase‐transformation temperature via a deformation mechanism‐based creep model

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