Gas Dynamics and Heat Transfer in a Packed Pebble-bed Reactor for the 4th Generation Nuclear Energy

Gas Dynamics and Heat Transfer in a Packed Pebble-bed Reactor for the 4th Generation Nuclear Energy PDF Author: Rahman Abdulmohsin
Publisher:
ISBN:
Category : Gas dynamics
Languages : en
Pages : 236

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Book Description
"Proper analyses of axial dispersion and mixing of the coolant gas flow and heat transport phenomena in the dynamic core of nuclear pebble-bed reactors pose extreme challenges to the safe design and efficient operation of these packed pebble-bed reactors. The main objectives of the present work are advancing the knowledge of the coolant gas dispersion and extent of mixing and the convective heat transfer coefficients in the studied packed pebble-beds. The study also provides the needed benchmark data for modeling and simulation validation. Hence, a separate effect pilot-plant scale and cold-flow experimental setup was designed, developed and used to carry out for the first time such experimental investigations. Advanced gaseous tracer technique was developed and utilized to measure in a cold-flow randomly packed pebble-bed unit the residence time distribution (RTD) of gas. A novel, sophisticated fast-response and non-invasive heat transfer probe of spherical type was developed and utilized to measure in a cold-flow packed pebble-bed unit the solid-gas convective heat transfer coefficients. The non-ideal flow of the gas phase in pebble bed was described using one-dimensional axial dispersion model (ADM), tanks-in-series (T-I-S) model and central moments analyses (CMA) method. Some of the findings of this study are: * The flow pattern of the gas phase does not much deviate from the idealized plug-flow condition which depends on the gas flow rate and bed structure of the pebble-bed. * The non-uniformity of gas flow in the studied packed pebble bed can be described adequately by the axial dispersion model (ADM) at different Reynolds numbers covers laminar and turbulent flow conditions. This has been further confirmed by the results of tanks in series (T-I-S) model and the central moment analyses (CMA). * The obtained results indicate that pebbles size and hence the bed structure strongly affects axial dispersion and mixing of the flowing coolant gas while the effect of bed height is negligible in packed pebble-bed. At high range of gas velocities, the change in heat transfer coefficients with respect to the gas velocity reduces as compared to these at low and medium range of gas velocities. * The increase of coolant gas flow velocity causes an increase in the heat transfer coefficient and the effect of gas flow rate varies from laminar to turbulent flow regimes at all radial positions of the studied packed pebble-bed reactor. * The results show that the local heat transfer coefficient increases from the bed center to the wall due to the change in the bed structure and hence in the flow pattern of the coolant gas. * The results and findings clearly indicate that one value as overall heat transfer coefficient cannot represent the local heat transfer coefficients within the bed and hence correlations to predict radial and axial profiles of heat transfer coefficient are needed"--Abstract, page iii.

Gas Dynamics and Heat Transfer in a Packed Pebble-bed Reactor for the 4th Generation Nuclear Energy

Gas Dynamics and Heat Transfer in a Packed Pebble-bed Reactor for the 4th Generation Nuclear Energy PDF Author: Rahman Abdulmohsin
Publisher:
ISBN:
Category : Gas dynamics
Languages : en
Pages : 236

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Book Description
"Proper analyses of axial dispersion and mixing of the coolant gas flow and heat transport phenomena in the dynamic core of nuclear pebble-bed reactors pose extreme challenges to the safe design and efficient operation of these packed pebble-bed reactors. The main objectives of the present work are advancing the knowledge of the coolant gas dispersion and extent of mixing and the convective heat transfer coefficients in the studied packed pebble-beds. The study also provides the needed benchmark data for modeling and simulation validation. Hence, a separate effect pilot-plant scale and cold-flow experimental setup was designed, developed and used to carry out for the first time such experimental investigations. Advanced gaseous tracer technique was developed and utilized to measure in a cold-flow randomly packed pebble-bed unit the residence time distribution (RTD) of gas. A novel, sophisticated fast-response and non-invasive heat transfer probe of spherical type was developed and utilized to measure in a cold-flow packed pebble-bed unit the solid-gas convective heat transfer coefficients. The non-ideal flow of the gas phase in pebble bed was described using one-dimensional axial dispersion model (ADM), tanks-in-series (T-I-S) model and central moments analyses (CMA) method. Some of the findings of this study are: * The flow pattern of the gas phase does not much deviate from the idealized plug-flow condition which depends on the gas flow rate and bed structure of the pebble-bed. * The non-uniformity of gas flow in the studied packed pebble bed can be described adequately by the axial dispersion model (ADM) at different Reynolds numbers covers laminar and turbulent flow conditions. This has been further confirmed by the results of tanks in series (T-I-S) model and the central moment analyses (CMA). * The obtained results indicate that pebbles size and hence the bed structure strongly affects axial dispersion and mixing of the flowing coolant gas while the effect of bed height is negligible in packed pebble-bed. At high range of gas velocities, the change in heat transfer coefficients with respect to the gas velocity reduces as compared to these at low and medium range of gas velocities. * The increase of coolant gas flow velocity causes an increase in the heat transfer coefficient and the effect of gas flow rate varies from laminar to turbulent flow regimes at all radial positions of the studied packed pebble-bed reactor. * The results show that the local heat transfer coefficient increases from the bed center to the wall due to the change in the bed structure and hence in the flow pattern of the coolant gas. * The results and findings clearly indicate that one value as overall heat transfer coefficient cannot represent the local heat transfer coefficients within the bed and hence correlations to predict radial and axial profiles of heat transfer coefficient are needed"--Abstract, page iii.

Multiphase Flow and Heat Transfer in Pebble Bed Reactor Core

Multiphase Flow and Heat Transfer in Pebble Bed Reactor Core PDF Author: Shengyao Jiang
Publisher: Springer Nature
ISBN: 9811595658
Category : Science
Languages : en
Pages : 510

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Book Description
This book introduces readers to gas flows and heat transfer in pebble bed reactor cores. It addresses fundamental issues regarding experimental and modeling methods for complex multiphase systems, as well as relevant applications and recent research advances. The numerical methods and experimental measurements/techniques used to solve pebble flows, as well as the content on radiation modeling for high-temperature pebble beds, will be of particular interest. This book is intended for a broad readership, including researchers and practitioners, and is sure to become a key reference resource for students and professionals alike.

Pebble Bed Reactor Program

Pebble Bed Reactor Program PDF Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category :
Languages : en
Pages : 252

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Book Description


Experimental and Computational Investigation of Flow of Pebbles in a Pebble Bed Nuclear Reactor

Experimental and Computational Investigation of Flow of Pebbles in a Pebble Bed Nuclear Reactor PDF Author: Vaibhav B. Khane
Publisher:
ISBN:
Category : Chemical reactors
Languages : en
Pages : 284

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Book Description
"The Pebble Bed Reactor (PBR) is a 4th generation nuclear reactor which is conceptually similar to moving bed reactors used in the chemical and petrochemical industries. In a PBR core, nuclear fuel in the form of pebbles moves slowly under the influence of gravity. Due to the dynamic nature of the core, a thorough understanding about slow and dense granular flow of pebbles is required from both a reactor safety and performance evaluation point of view. In this dissertation, a new integrated experimental and computational study of granular flow in a PBR has been performed. Continuous pebble re-circulation experimental set-up, mimicking flow of pebbles in a PBR, is designed and developed. Experimental investigation of the flow of pebbles in a mimicked test reactor was carried out for the first time using non-invasive radioactive particle tracking (RPT) and residence time distribution (RTD) techniques to measure the pebble trajectory, velocity, overall/zonal residence times, flow patterns etc. The tracer trajectory length and overall/zonal residence time is found to increase with change in pebble's initial seeding position from the center towards the wall of the test reactor. Overall and zonal average velocities of pebbles are found to decrease from the center towards the wall. Discrete element method (DEM) based simulations of test reactor geometry were also carried out using commercial code EDEM and simulation results were validated using the obtained benchmark experimental data. In addition, EDEM based parametric sensitivity study of interaction properties was carried out which suggests that static friction characteristics play an important role from a packed/pebble beds structural characterization point of view. To make the RPT technique viable for practical applications and to enhance its accuracy, a novel and dynamic technique for RPT calibration was designed and developed. Preliminary feasibility results suggest that it can be implemented as a non-invasive and dynamic calibration methodology for RPT technique which will enable its industrial applications."--Abstract, page iii.

Gas Cooled Pebble Bed Reactor for a Large Central Station

Gas Cooled Pebble Bed Reactor for a Large Central Station PDF Author:
Publisher:
ISBN:
Category : Feasibility studies
Languages : en
Pages : 324

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Fuel Element Development Program for the Pebble Bed Reactor

Fuel Element Development Program for the Pebble Bed Reactor PDF Author: Sanderson & Porter, Inc
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 142

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Book Description
Numerous types of high temperature ceramic fuel elements for the Pebble Bed Reactor are being evaluated. Specimens are 1-1/2 in diameter uranium graphite spheres with external coatings such as silicon carbide or pyrolytically deposited high density graphite and feul particle coatings such as alumina. Low diffusion product leakage rates at high temperatures have been observed for some of these coatings. High level irradiation damage to either the silicon carbide coating or the coating-graphite bond.

Fuel Element Development Program for the Pebble Bed Reactor

Fuel Element Development Program for the Pebble Bed Reactor PDF Author:
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 142

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Book Description


Pebble Bed Reactors Design Optimization Methods and Their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR)

Pebble Bed Reactors Design Optimization Methods and Their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR) PDF Author: Anselmo Tomas Cisneros
Publisher:
ISBN:
Category :
Languages : en
Pages : 859

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Book Description
The Fluoride salt cooled High temperature Reactor (FHR) is a class of advanced nuclear reactors that combine the robust coated particle fuel form from high temperature gas cooled reactors, direct reactor auxillary cooling system (DRACS) passive decay removal of liquid metal fast reactors, and the transparent, high volumetric heat capacitance liquid fluoride salt working fluids - flibe (33%7Li2F-67%BeF) - from molten salt reactors. This combination of fuel and coolant enables FHRs to operate in a high-temperature low-pressure design space that has beneficial safety and economic implications. In 2012, UC Berkeley was charged with developing a pre-conceptual design of a commercial prototype FHR - the Pebble Bed- Fluoride Salt Cooled High Temperature Reactor (PB-FHR) - as part of the Nuclear Energy University Programs' (NEUP) integrated research project. The Mark 1 design of the PB-FHR (Mk1 PB-FHR) is 236 MWt flibe cooled pebble bed nuclear heat source that drives an open-air Brayton combine-cycle power conversion system. The PB-FHR's pebble bed consists of a 19.8% enriched uranium fuel core surrounded by an inert graphite pebble reflector that shields the outer solid graphite reflector, core barrel and reactor vessel. The fuel reaches an average burnup of 178000 MWt-d/MT. The Mk1 PB-FHR exhibits strong negative temperature reactivity feedback from the fuel, graphite moderator and the flibe coolant but a small positive temperature reactivity feedback of the inner reflector and from the outer graphite pebble reflector. A novel neutronics and depletion methodology - the multiple burnup state methodology was developed for an accurate and efficient search for the equilibrium composition of an arbitrary continuously refueled pebble bed reactor core. The Burnup Equilibrium Analysis Utility (BEAU) computer program was developed to implement this methodology. BEAU was successfully benchmarked against published results generated with existing equilibrium depletion codes VSOP and PEBBED for a high temperature gas cooled pebble bed reactor. Three parametric studies were performed for exploring the design space of the PB-FHR -- to select a fuel design for the PB-FHR] to select a core configuration; and to optimize the PB-FHR design. These parametric studies investigated trends in the dependence of important reactor performance parameters such as burnup, temperature reactivity feedback, radiation damage, etc on the reactor design variables and attempted to understand the underlying reactor physics responsible for these trends. A pebble fuel parametric study determined that pebble fuel should be designed with a carbon to heavy metal ratio (C/HM) less than 400 to maintain negative coolant temperature reactivity coefficients. Seed and thorium blanket-, seed and inert pebble reflector- and seed only core configurations were investigated for annular FHR PBRs - the C/HM of the blanket pebbles and discharge burnup of the thorium blanket pebbles were additional design variable for core configurations with thorium blankets. Either a thorium blanket or graphite pebble reflector is required to shield the outer graphite reflector enough to extend its service lifetime to 60 EFPY. The fuel fabrication costs and long cycle lengths of the thorium blanket fuel limit the potential economic advantages of using a thorium blanket. Therefore, the seed and pebble reflector core configuration was adopted as the baseline core configuration. Multi-objective optimization with respect to economics was performed for the PB-FHR accounting for safety and other physical design constraints derived from the high-level safety regulatory criteria. These physical constraints were applied along in a design tool, Nuclear Application Value Estimator, that evaluated a simplified cash flow economics model based on estimates of reactor performance parameters calculated using correlations based on the results of parametric design studies for a specific PB-FHR design and a set of economic assumptions about the electricity market to evaluate the economic implications of design decisions. The optimal PB-FHR design - Mark 1 PB-FHR - is described along with a detailed summary of its performance characteristics including: the burnup, the burnup evolution, temperature reactivity coefficients, the power distribution, radiation damage distributions, control element worths, decay heat curves and tritium production rates. The Mk1 PB-FHR satisfies the PB-FHR safety criteria. The fuel, moderator (pebble core, pebble shell, graphite matrix, TRISO layers) and coolant have global negative temperature reactivity coefficients and the fuel temperatures are well within their limits.

Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor

Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor PDF Author: Brian Boer
Publisher:
ISBN: 9781586039660
Category : Nuclear fuels
Languages : en
Pages : 0

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Book Description
The Very High Temperature Reactor (VHTR) has been selected by the international Generation IV research initiative as one of the six most promising nuclear reactor concepts that are expected to enter service in the second half of the 21st century. As one of the fourth generation nuclear reactors, the VHTR is characterized by high plant efficiency and a high fuel discharge burn-up level. More specifically, the (pebble-bed type) High Temperature Reactor (HTR) is known for its inherently safe characteristics, coming from a negative temperature reactivity feedback, a low power density and a large thermal inertia of the core.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 516

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Book Description