Computational study of full-scale VHTR lower plenum for turbulent mixing assessment

Clifford, Corey E.; Fradeneck, Austen; Oler, Adam M.; Salkhordeh, Sasan; Kimber, Mark

doi:10.1016/j.anucene.2019.05.055

Cited by 9 publications

(3 citation statements)

References 14 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Lower plenum flow modeling is needed to address both potential issues. As illustrated in Figure 3, the CFD simulation at the lower plenum of the prismatic HTGR design performed by Clifford et al [20] has demonstrated the multifaceted nature of lower plenum thermalhydraulics with numerous fundamental processes (thermal stratification, turbulent mixing, vortex shedding, etc.) distinctly exhibited throughout the domain.…”

Section: Lower Plenummentioning

confidence: 99%

See 1 more Smart Citation

High-Temperature Gas-Cooled Reactor Research Survey and Overview: Preliminary Data Platform Construction for the Nuclear Energy University Program

Qin

Minseop

Vietz

et al. 2022

View full text Add to dashboard Cite

Since the U.S. Department of Energy Office of Nuclear Energy initiated the Nuclear Energy University Program (NEUP) in 2009, there are 29 NEUP projects focusing on high-temperature gas-cooled reactor (HTGR) research up to July 2022. The resultant research product, either experimental or computational, were published as final NEUP reports, journal articles and conference proceedings. However, these federally funded products have been scattered and sometimes cannot be easily accessed.To improve access to this valuable HTGR validation data and optimize the return on the significant investment made by the Department of Energy, the Advanced Reactor Technologies (ART) Gas-Cooled Reactor (GCR) program started a survey of completed and ongoing HTGR NEUP projects to develop a public-access database specific for HTGRs applications that can be used to retrieve computational fluid dynamics and system code validation data. This effort will help guide future NEUP-funded research, define new state of the ART Phenomena Identification and Ranking Table (PIRT), and promote the usage of this data in the codes validation matrices. This report provides an overview of the NEUP-funded HTGR-related research projects from Fiscal Year (FY) 2009-2021 and identifies validation knowledge gaps still existing in HTGR thermal-fluid research.A preliminary data platform has been developed for the 29 NEUP projects investigating HTGR thermal hydraulics, including their final reports as well as the available scientific publications. As an ultimate goal for this work, the ART-GCR program will create a central database at Idaho National Laboratory to identify, organize, and store these datasets generated by experimental investigations or computational models, experimental facility descriptions, and publicly-available academic products from the HTGR-related NEUP projects and provide future guidance for the storage and transmission of important project documentations for later NEUP projects as well.

show abstract

Section: Lower Plenummentioning

confidence: 99%

“…Coolant streamlines colored by temperature (K) in lower plenum of a prismatic HTGR design. Adapted from [20].…”

Section: Lower Plenummentioning

confidence: 99%

High-Temperature Gas-Cooled Reactor Research Survey and Overview: Preliminary Data Platform Construction for the Nuclear Energy University Program

Qin

Minseop

Vietz

et al. 2022

View full text Add to dashboard Cite

show abstract

“…The single round jet has received extensive devotion in the literature due to its existence in a variety of real-world applications. The study of such jets exist in fields relative to the design of electronic component cooling [1][2][3][4], the mixing of hot and cold fluid streams [5][6][7][8], and for this particular study, a preliminary analysis of importance in very high temperature reactors (VHTR).…”

Section: Introductionmentioning

confidence: 99%

Hydraulic Comparison of Single and Multiple-Jet Impingement on a Flat Plate

Reed

Weiss

Kristo

et al. 2020

Proceeding of 5th Thermal and Fluids Engineering Conference (TFEC)

Self Cite

View full text Add to dashboard Cite

Jet impingement onto a solid boundary is of practical interest in a variety of engineering applications. The novelty of the current work is in the comparison of the single and multiple inline jets, the latter being more prevalent in application but less examined in the literature. The study focuses explicitly on the incompressible, hydraulic comparison, by performing experiments near room temperature and low speeds. Three round jets of diameter 22.23 mm are placed inline and 2 diameters apart on the ceiling of the test section. The jets issue vertically downward into a pseudo-unconfined domain whose bottom surface is 9.8 diameters from the jet outlets, acting as the plate. Three distinct flow rates are measured via Stereoscopic Particle Image Velocimetry (S-PIV) for both the single jet and triple jet geometries, where for the latter, each outlet is set to an equivalent flow rate. Several reference parameters further delineate fluid properties in the test section and ambient environment. The investigation begins with evaluation of the single jet, comparing first and second order turbulence statistics with existing literature. The triple jet cases are then presented, showing dramatically different behavior. The results of each configuration, inlet profiles, reference parameters, and uncertainty quantification are provided to embolden future work in computational fluid dynamics (CFD). The investigation concludes with the promotion of several comparisons of the single and triple jet setup and is meant to provide insight into the expected dynamic response of the fluid near and along the solid boundary.

show abstract

Design of an experimental facility with a unit cell test section for studies of the lower plenum in prismatic high temperature gas reactors

Landfried

Kristo

Clifford

et al. 2019

Annals of Nuclear Energy

View full text Add to dashboard Cite

Computational study of full-scale VHTR lower plenum for turbulent mixing assessment

Cited by 9 publications

References 14 publications

High-Temperature Gas-Cooled Reactor Research Survey and Overview: Preliminary Data Platform Construction for the Nuclear Energy University Program

High-Temperature Gas-Cooled Reactor Research Survey and Overview: Preliminary Data Platform Construction for the Nuclear Energy University Program

Hydraulic Comparison of Single and Multiple-Jet Impingement on a Flat Plate

Design of an experimental facility with a unit cell test section for studies of the lower plenum in prismatic high temperature gas reactors

Contact Info

Product

Resources

About