Open Access. Powered by Scholars. Published by Universities.®
- Keyword
-
- Accidents (1)
- Bubble Diameter (1)
- Conduction cooldown (1)
- Conductivity (1)
- Conjugate Heat Transfer (1)
-
- Experimental investigations (1)
- Four-Sensor (1)
- Heat flux (1)
- Heat flux distributions (1)
- Heat flux intensity (1)
- Heat transfer coefficients (1)
- Heat transfer technique (1)
- Hydraulics (1)
- Interfacial Area Concentration (1)
- Lower Plenum (1)
- Modular reactors (1)
- Natural convection (1)
- Non-uniform heat fluxes (1)
- Nonuniform heat flux (1)
- Optical (1)
- Passive safety features (1)
- Pressurized conduction cooldown accidents (1)
- Pressurizer (1)
- Prismatic modular reactors (1)
- Reactor Core (1)
- Small Modular Reactor (1)
- Transfer technique (1)
- Turbulent Flow (1)
- Two-Phase (1)
- Publication
- Publication Type
Articles 1 - 3 of 3
Full-Text Articles in Nuclear Engineering
Experimental Investigation On Heat Transfer In A Prismatic Modular Reactor Under Cosine Heat Flux, S. M. Alshehri, I. A. Said, Muthanna H. Al-Dahhan, Shoaib Usman
Experimental Investigation On Heat Transfer In A Prismatic Modular Reactor Under Cosine Heat Flux, S. M. Alshehri, I. A. Said, Muthanna H. Al-Dahhan, Shoaib Usman
Chemical and Biochemical Engineering Faculty Research & Creative Works
The current study has investigated natural convection heat during pressurized conduction cooldown (PCC) accident scenario to understand the passive safety features of prismatic modular reactors (PMR) under different intensities of nonuniform center peaking step heat flux distributions (approximating cosine shape) using an advanced fast-response heat transfer technique. A scaled-down PMR module was designed and developed at Missouri S&T by the research team of the Multiphase Reactors Engineering and Applications Laboratory (mReal). The module consists of upper and lower plena connected by heated and cooled channels. Nonuniform heat flux distribution was applied to the heated channel under nonuniform heating center peaking …
Computational Design And Numerical Analyses Of Thermal-Hydraulics In A Pwr-Type Small Modular Nuclear Reactor, Vivek Murlidhar Rao
Computational Design And Numerical Analyses Of Thermal-Hydraulics In A Pwr-Type Small Modular Nuclear Reactor, Vivek Murlidhar Rao
Doctoral Dissertations
"This dissertation focuses on computational design of a PWR-type small modular nuclear reactor (SMR), and analysis of coolant thermal-hydraulics during steady-state operation. Physical design of the SMR is based on the existing AP-1000 and Small Modular Reactor designs by Westinghouse Nuclear.
The first paper discusses a two-stage simulation of turbulent flow in the lower plenum of the RPV. In the first stage, four time-dependent Reynolds-Averaged Navier-Stokes (RANS) based turbulence models were used to simulate turbulent flow, compare predictions and identify an appropriate turbulence model. In the second stage, the selected turbulence model was once again used to simulate flow on …
The Significance Of Grouping And Missed Bubbles On Interfacial Area Concentration And Void Fraction, Chandller Stephen-Leslie Mills
The Significance Of Grouping And Missed Bubbles On Interfacial Area Concentration And Void Fraction, Chandller Stephen-Leslie Mills
Doctoral Dissertations
"The two-fluid model is used in nuclear reactor safety codes. Two of the important constitutive relations will be discussed in this study, the interfacial area concentration and void fraction. The Interfacial area concentration is directly affected by the number of bubbles and how these bubbles are categorized into groups. In this study, a new algorithm was implemented to account for trailing bubbles, bubbles with short response times, and the categorization of bubbles based upon diameter for all group 1 bubbles. The optical and conductivity probes were used to determine the void fraction and interfacial area concentration in a bubble column. …