Experimental investigation of BWR Suppression Pool stratification during RCIC system operation

Solom, Matthew; Kirkland, Karen Vierow

doi:10.1016/j.nucengdes.2016.10.045

Cited by 25 publications

(11 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Additional efforts are underway to assess the effects of SRV and RCIC operation on stratification within the containment. [303] Evaluations with the enhanced MAAP models are being applied to predict instrumentation readings available to operators during severe accidents (and identify potential false instrumentation readings). Hence, reduced uncertainties in systems analysis code predictions provide additional confidence in severe accident management guidance in the U.S. Evaluations with these codes are also useful to Japan as input for D&D Phase II assessments.…”

Section: E22 Code Modeling Enhancementsmentioning

confidence: 99%

U.S. Efforts in Support of Examinations at Fukushima Daiichi: 2019 Evaluations

Amway¹,

Andrews²,

Basu³

et al. 2019

View full text Add to dashboard Cite

Much is still not known about the end-state of core materials in each unit that was operating on March 11, 2011 at the Fukushima Daiichi Nuclear Power Station (Daiichi). Information obtained from Daiichi is required to inform Decontamination and Decommissioning (D&D) activities, improving the ability of the Tokyo Electric Power Company Holdings, Incorporated (TEPCO Holdings) to characterize potential hazards and to ensure the safety of workers involved with cleanup activities. This document, which has been updated to include Fiscal Year 2019 (FY2019) information, summarizes results from a U.S. effort to review Daiichi information and extract insights to enhance the safety of existing and future nuclear power plant designs. This U.S. effort, which was initiated in 2014 by the Department of Energy Office of Nuclear Energy (DOE-NE), is completed by a group of experts in reactor safety and plant operations that identify examination needs and evaluate recent Daiichi examination data to address these needs. Each year, annual reports are issued that document significant safety insights being obtained in areas of special emphasis. For FY2019, the areas emphasized by the expert panel include component performance, radionuclide surveys and sampling, debris end-state location, combustible gas effects, and plant operations and maintenance. In addition to reducing uncertainties related to severe accident modeling progression, these insights have and continue to be used to update guidance for severe accident prevention, mitigation, and emergency planning. Reduced uncertainties in modeling the events at Daiichi improve the realism of reactor safety evaluations that inform future D&D activities. In addition, the process established by this U.S. effort provides an example that Japan may wish to implement in future international efforts to support D&D.

show abstract

Section: E22 Code Modeling Enhancementsmentioning

confidence: 99%

U.S. Efforts in Support of Examinations at Fukushima Daiichi: 2019 Evaluations

Amway¹,

Andrews²,

Basu³

et al. 2019

View full text Add to dashboard Cite

show abstract

“…This resulted in similar initial conditions, which could be the reason for the similarity of during the low steam injection phases, which later led to larger steam pressures and temperatures in PPOOLEX (about 10 kPa larger). Work done by [43] shows that, for the same injection rates, a pressurized vessel leads to a stronger thermal stratification in the pool. This effect was attributed to the changes on the steam density, an effect which is already taken into account in the EMS sparger model, equation (6).…”

Section: Calibration Of the Momentum Sourcesmentioning

confidence: 99%

Pool stratification and mixing induced by steam injection through spargers: CFD modelling of the PPOOLEX and PANDA experiments

Gallego-Marcos

Kudinov

Villanueva

et al. 2019

Nuclear Engineering and Design

View full text Add to dashboard Cite

Spargers are multi-hole injection pipes used in Boiling Water Reactors (BWR) and Generation III/III+ Pressurized Water Reactors (PWR) to condense steam in large water pools. During the steam injection, high pool surface temperatures induced by thermal stratification can lead to higher containment pressures compared with completely mixed pool conditions, the former posing a threat for plant safety. The Effective Heat Source (EHS) and Effective Momentum Source (EMS) models were previously developed and validated for the modelling of a steam injection through blowdown pipes. The goal of this paper is to extend the EHS/EMS model capabilities towards steam injection through multi-hole spargers. The models are implemented in ANSYS Fluent 17.0 Computational Fluid Dynamics (CFD) code and calibrated against the spargers experiments performed in the PPOOLEX and PANDA facilities, analysed by the authors in [1] (Gallego-Marcos, I., et al., 2018). CFD modelling guidelines are established for the adequate simulation of the pool behaviour. A new correlation is proposed to model the turbulent production and dissipation caused by buoyancy. Sensitivity studies addressing the effect of different assumptions on the effective momentum magnitude, profile, angle and turbulence are presented. Calibration of the effective momentum showed an inverse proportionality to the sub-cooling. Differences between the effective momentum calibrated for PPOOLEX and PANDA are discussed. Analysis of the calculated flow above the cold stratified layer showed that the erosion of the layer is induced by the action of turbulence rather than mean shear flow.

show abstract

“…Regeneration is required after approximately 350 gallons are purified because relatively high levels of total dissolved solids are in the water supply. This system was installed in the facility prior to the start of the ZS-1 experiment ( [Solom, 2016] and [Solom and Kirkland, 2016]).…”

Section: Water Deionization Systemmentioning

confidence: 99%