Relevant bibliographies by topics / Pebble bed reactors – Cooling

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Pebble bed reactors – Cooling'

Author: Grafiati
Published: 4 June 2021
Last updated: 8 February 2022

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Pebble bed reactors – Cooling.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Journal articles on the topic "Pebble bed reactors – Cooling"

1

Song, Shixiong, Xiangzhou Cai, Yafen Liu, Quan Wei, and Wei Guo. "Pore Scale Thermal Hydraulics Investigations of Molten Salt Cooled Pebble Bed High Temperature Reactor with BCC and FCC Configurations." Science and Technology of Nuclear Installations 2014 (2014): 1–16. http://dx.doi.org/10.1155/2014/589895.

Full text
Abstract:
The present paper systematically investigated pore scale thermal hydraulics characteristics of molten salt cooled high temperature pebble bed reactor. By using computational fluid dynamics (CFD) methods and employing simplified body center cubic (BCC) and face center cubic (FCC) model, pressure drop and local mean Nusselt number are calculated. The simulation result shows that the high Prandtl number molten salt in packed bed has unique fluid-dynamics and thermodynamic properties. There are divergences between CFD results and empirical correlations’ predictions of pressure drop and local Nusse
APA, Harvard, Vancouver, ISO, and other styles
2

Langston, Lee S. "PBMR-A Future Failsafe Gas Turbine Nuclear Power Plant?" Mechanical Engineering 133, no. 08 (2011): 54–59. http://dx.doi.org/10.1115/1.2011-aug-5.

Full text
Abstract:
This article presents an overview of a pebble bed modular reactor (PBMR) power plant. A PBMR power plant is a gas turbine nuclear power plant that completely eliminates the possibility of a devastating loss-of-coolant accident. In a PBMR power plant, uranium dioxide nuclear fuel, coated with mass diffusion and radioactive fission product containment layers of pyrolytic carbon and silicon carbide, is formed into nuclear poppy seed-sized fuel particles. Some 15,000 of these are embedded in a tennis ball-sized graphite sphere, which is encased in a thin carbon shell, sintered, annealed and machin
APA, Harvard, Vancouver, ISO, and other styles
3

Moormann, Rainer. "Fission Product Transport and Source Terms in HTRs: Experience from AVR Pebble Bed Reactor." Science and Technology of Nuclear Installations 2008 (2008): 1–14. http://dx.doi.org/10.1155/2008/597491.

Full text
Abstract:
Fission products deposited in the coolant circuit outside of the active core play a dominant role in source term estimations for advanced small pebble bed HTRs, particularly in design basis accidents (DBA). The deposited fission products may be released in depressurization accidents because present pebble bed HTR concepts abstain from a gas tight containment. Contamination of the circuit also hinders maintenance work. Experiments, performed from 1972 to 88 on the AVR, an experimental pebble bed HTR, allow for a deeper insight into fission product transport behavior. The activity deposition per
APA, Harvard, Vancouver, ISO, and other styles
4

Sadeghi, H., and M. Habibi. "Design and simulation of a blanket module for TOKAMAK reactors." Modern Physics Letters A 34, no. 13 (2019): 1950103. http://dx.doi.org/10.1142/s0217732319501037.

Full text
Abstract:
In this paper, we simulated an appropriate model for an advanced breeding blanket of future TOKAMAK fusion reactors with solid breeder (Li4SiO4) building material in the form of pebble beds, ODS ferritic steel as structural material and Beryllium as neutron multiplier. With the MCNPX code, the efficiency of this proposed model for the production and self-sufficiency of tritium was investigated. Total tritium breeding ratio of 1.15 is achieved. The helium-cooled pebble bed system and parameters of temperature and pressure are investigated by COMSOL multiphysics simulating software. The temperat
APA, Harvard, Vancouver, ISO, and other styles
5

Strydom, Gerhard. "Uncertainty and Sensitivity Analyses of a Pebble Bed HTGR Loss of Cooling Event." Science and Technology of Nuclear Installations 2013 (2013): 1–16. http://dx.doi.org/10.1155/2013/426356.

Full text
Abstract:
The Very High Temperature Reactor Methods Development group at the Idaho National Laboratory identified the need for a defensible and systematic uncertainty and sensitivity approach in 2009. This paper summarizes the results of an uncertainty and sensitivity quantification investigation performed with the SUSA code, utilizing the International Atomic Energy Agency CRP 5 Pebble Bed Modular Reactor benchmark and the INL code suite PEBBED-THERMIX. Eight model input parameters were selected for inclusion in this study, and after the input parameters variations and probability density functions wer
APA, Harvard, Vancouver, ISO, and other styles
6

Forsberg, Charles W., and Per F. Peterson. "FHR, HTGR, and MSR Pebble-Bed Reactors with Multiple Pebble Sizes for Fuel Management and Coolant Cleanup." Nuclear Technology 205, no. 5 (2019): 748–54. http://dx.doi.org/10.1080/00295450.2019.1573619.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Sidi-Ali, Kamel, Khaled Oukil, Tinhinane Hassani, Yasmina Amri, and Abdelmoumane Alem. "Evaluation of radiation heat transfer in porous medial: Application for a pebble bed modular reactor cooled by CO2 gas." Nuclear Technology and Radiation Protection 28, no. 2 (2013): 118–27. http://dx.doi.org/10.2298/ntrp1302118s.

Full text
Abstract:
This work analyses the contribution of radiation heat transfer in the cooling of a pebble bed modular reactor. The mathematical model, developed for a porous medium, is based on a set of equations applied to an annular geometry. Previous major works dealing with the subject have considered the forced convection mode and often did not take into account the radiation heat transfer. In this work, only free convection and radiation heat transfer are considered. This can occur during the removal of residual heat after shutdown or during an emergency situation. In order to derive the governing equat
APA, Harvard, Vancouver, ISO, and other styles
8

Gonfiotti, Bruno, and Sandro Paci. "Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept." Science and Technology of Nuclear Installations 2015 (2015): 1–9. http://dx.doi.org/10.1155/2015/865829.

Full text
Abstract:
As for Light Water Reactors (LWRs), one of the most challenging accidents for the future DEMOnstration power plant is the Loss of Coolant Accident, which can trigger the pressurization of the confinement structures and components. Hence, careful analyses have to be executed to demonstrate that the confinement barriers are able to withstand the pressure peak within design limits and the residual cooling capabilities of the Primary Heat Transfer System are sufficient to remove the decay heat. To do so, severe accident codes, as MELCOR, can be employed. In detail, the MELCOR code has been develop
APA, Harvard, Vancouver, ISO, and other styles
9

Sun, Shiyan, Youjie Zhang, and Yanhua Zheng. "Research on Influence of Different Simulation Methods of Bypass Flow in Thermal Hydraulic Analysis on Temperature Distribution in HTR-10." Science and Technology of Nuclear Installations 2020 (June 26, 2020): 1–8. http://dx.doi.org/10.1155/2020/4754589.

Full text
Abstract:
In pebble-bed high temperature gas-cooled reactor, gaps widely exist between graphite blocks and carbon bricks in the reactor core vessel. The bypass helium flowing through the gaps affects the flow distribution of the core and weakens the effective cooling of the core by helium, which in turn affects the temperature distribution and the safety features of the reactor. In this paper, the thermal hydraulic analysis models of HTR-10 with bypass flow channels simulated at different positions are designed based on the flow distribution scheme of the original core models and combined with the actua
APA, Harvard, Vancouver, ISO, and other styles
10

Xie, F., W. Peng, J. Cao, et al. "Experimental Investigation of 14C in the Primary Coolant of the 10 MW High Temperature Gas-Cooled Reactor." Radiocarbon 61, no. 03 (2019): 867–84. http://dx.doi.org/10.1017/rdc.2019.6.

Full text
Abstract:
ABSTRACTThe very high temperature reactor (VHTR) is a development of the high-temperature gas-cooled reactors (HTGRs) and one of the six proposed Generation IV reactor concept candidates. The 10 MW high temperature gas-cooled reactor (HTR-10) is the first pebble-bed gas-cooled test reactor in China. A sampling system for the measurement of carbon-14 (14C) was established in the helium purification system of the HTR-10 primary loop, which could sample 14C from the coolant at three locations. The results showed that activity concentration of 14C in the HTR-10 primary coolant was 1.2(1) × 102 Bq/
APA, Harvard, Vancouver, ISO, and other styles
More sources

Dissertations / Theses on the topic "Pebble bed reactors – Cooling"

1

Ruppersberg, Johannes Coenraad. "Transient modelling of a loop thermosyphon : transient effects in single and two phase natural circulation thermosyphon loops suitable for the reactor cavity cooling of a pebble bed modular reactor." Thesis, Stellenbosch : Stellenbosch University, 2008. http://hdl.handle.net/10019.1/20858.

Full text
Abstract:
Thesis (MScIng)--University of Stellenbosch, 2008.<br>ENGLISH ABSTRACT: The focus of this project was the application of a passive device in the form of a loop thermosyphon as a reactor cavity cooling system (RCCS) for a Pebble Bed Modular Reactor. An extensive literature review showed that loop thermosyphons have been widely researched, both theoretically and experimentally. In the review attention has specifically been given to matters such as safety, instability, control and mathematical modelling. One of the objectives of the project was to build one of the axially symmetric sections
APA, Harvard, Vancouver, ISO, and other styles
2

Verwey, Aldo. "Modelling of a passive reactor cavity cooling system (RCCS) for a nuclear reactor core subject to environmental changes and the optimisation of the RCCS radiation heat shield heat shield." Thesis, Stellenbosch : University of Stellenbosch, 2010. http://hdl.handle.net/10019.1/4303.

Full text
Abstract:
Thesis (MScEng (Mechanical and Mechatronic Engineering))--University of Stellenbosch, 2010.<br>ENGLISH ABSTRACT: A reactor cavity cooling system (RCCS) is used in the PBMR to protect the concrete citadel surrounding the reactor from direct nuclear radiation impingement and heat. The speci ed maximum operating temperature of the concrete structure is 65 ±C for normal operating conditions and 125 ±C for emergency shut-down conditions. A conceptual design of an entirely passive RCCS suitable for the PBMR was done by using closed loop thermosyphon heat pipes (CLTHPs) to remove heat from a rad
APA, Harvard, Vancouver, ISO, and other styles
3

Sittmann, Ilse. "Inside-pipe heat transfer coefficient characterisation of a one third height scale model of a natural circulation loop suitable for a reactor cavity cooling system of the Pebble Bed Modular Reactor." Thesis, Stellenbosch : University of Stellenbosch, 2011. http://hdl.handle.net/10019.1/6708.

Full text
Abstract:
Thesis (MScEng (Mechanical and Mechatronic Engineering))--University of Stellenbosch, 2011.<br>ENGLISH ABSTRACT: The feasibility of a closed loop thermosyphon for the Reactor Cavity Cooling System of the Pebble Bed Modular Reactor has been the subject of many research projects. Difficulties identified by previous studies include the hypothetical inaccuracies of heat transfer coefficient correlations available in literature. The aim of the research presented here is to develop inside-pipe heat transfer correlations that are specific to the current design of the RCCS. In order to achieve t
APA, Harvard, Vancouver, ISO, and other styles
4

Oosthuizen, Philip Rudolf. "Thermal-fluid simulation investigation of the reactor cavity cooling system standpipes design for the pebble bed modular reactor / P.R. Oosthuizen." Thesis, North-West University, 2003. http://hdl.handle.net/10394/518.

Full text
Abstract:
Pebble Bed Modular Reactors are advanced nuclear reactors and are being developed to possess inherent safety and reliability. This is achieved by utilizing a sequence of passive thermal storage and heat transfer mechanisms, to perform long term decay heat removal. The Reactor Cavity Cooling System (RCCS) facilitates this long term decay heat removal. The purpose of this study was to develop a one-dimensional, homogeneous two-phase flow model in order to perform investigative thermal-fluid studies on the concept designs of the standpipes of a typical RCCS system, such as that proposed for PBMR
APA, Harvard, Vancouver, ISO, and other styles
5

Van, der Merwe David-John. "Experimental and numerical investigation of the heat transfer between a high temperature reactor pressure vessel and the outside of the concrete confinement structure." Thesis, Stellenbosch : Stellenbosch University, 2012. http://hdl.handle.net/10019.1/71796.

Full text
Abstract:
Thesis (MScEng)--Stellenbosch University, 2012.<br>ENGLISH ABSTRACT: A high temperature reactor (HTR) generates heat inside of the reactor core through nuclear fission, from where the heat is transferred through the core and heats up the reactor pressure vessel (RPV). The heat from the RPV is transported passively through the reactor cavity, where it is cooled by the reactor cavity cooling system (RCCS), through the concrete confinement structure and ultimately into the environment. The concrete confinement structure can withstand temperatures of up to 65°C for normal operating conditions
APA, Harvard, Vancouver, ISO, and other styles
6

Lebenhaft, Julian R. (Julian Robert) 1954. "MCNP4B modeling of pebble-bed reactors." Thesis, Massachusetts Institute of Technology, 2001. http://hdl.handle.net/1721.1/28288.

Full text
Abstract:
Thesis (Nucl.E. and S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, February 2002.<br>Includes bibliographical references (v. 1, leaves 152-171).<br>The applicability of the Monte Carlo code MCNP4B to the neutronic modeling of pebblebed reactors was investigated. A modeling methodology was developed based on an analysis of critical experiments carried out at the HTR-PROTIEUS and ASTRA facilities, and the critical loading of the HTR-10 reactor. A body-centred cubic lattice of spheres with a specified packing fraction approximates the pebble bed, and exclusion zones o
APA, Harvard, Vancouver, ISO, and other styles
7

Abejón, Orzáez Jorge. "Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor." Columbus, Ohio : Ohio State University, 2009. http://rave.ohiolink.edu/etdc/view?acc%5Fnum=osu1238045558.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Yesilyurt, Gokhan. "Numerical simulation of flow distribution for pebble bed high temperature gas cooled reactors." Texas A&M University, 2004. http://hdl.handle.net/1969.1/372.

Full text
Abstract:
The premise of the work presented here is to use a common analytical tool, Computational Fluid dynamics (CFD), along with a difference turbulence models. Eddy viscosity models as well as state-of-the-art Large Eddy Simulation (LES) were used to study the flow past bluff bodies. A suitable CFD code (CFX5.6b) was selected and implemented. Simulation of turbulent transport for the gas through the gaps of the randomly distributed spherical fuel elements (pebbles) was performed. Although there are a number of numerical studies () on flows around spherical bodies, none of them use the necessary turb
APA, Harvard, Vancouver, ISO, and other styles
9

Movalo, Raisibe Shirley. "Fuel management study for a pebble bed modular reactor core." Thesis, Stellenbosch : Stellenbosch University, 2010. http://hdl.handle.net/10019.1/4234.

Full text
Abstract:
Thesis (MSc (Physics))--Stellenbosch University, 2010.<br>ENGLISH ABSTRACT: This dissertation reports on the impact of a set of selected nuclear fuel management parameters on reactor operations of the PBMR core. This is achieved by performing an assessment of the impact of nuclear fuel management parameter variations on the most important safety and economics issues for the PBMR core. These include the maximum fuel temperature at steady state and during Depressurized Loss of Forced Cooling (DLOFC) accident conditions. The reactivity worth of the Reactor Control System (RCS which determin
APA, Harvard, Vancouver, ISO, and other styles
10

Mashau, Sharon Ntevheleni. "The preparation of pitches from anthracene oil." Pretoria : [S.n.], 2007. http://upetd.up.ac.za/thesis/available/etd-06242008-075035/.

Full text
APA, Harvard, Vancouver, ISO, and other styles
More sources

Books on the topic "Pebble bed reactors – Cooling"

1

Boer, Brian. Optimized core design and fuel management of a pebble-bed type nuclear reactor. IOS Press, 2008.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
2

A, Verrall R., Atomic Energy of Canada Limited., and Chalk River Laboratories. Fuel Development Branch, eds. Post-irradiation examination of BEATRIX-II phase-II Li2ZrO3 pebble-bed. Fuel Development Branch, Chalk River Laboratories, 1996.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
3

(Germany), Arbeitsgemeinschaft Versuchsreaktor, Kernforschungsanlage Jülich, and VDI-Gesellschaft Energietechnik, eds. AVR, 20 Jahre Betrieb: Ein deutscher Beitrag zu einer zukunftsweisenden Energietechnik : Tagung Aachen, 17. und 18. Mai 1989. VDI-Verlag, 1989.

Find full text
APA, Harvard, Vancouver, ISO, and other styles

Book chapters on the topic "Pebble bed reactors – Cooling"

1

Suikkanen, Heikki, Ville Rintala, and Juhani Hyvärinen. "DEM in Analyses of Nuclear Pebble Bed Reactors." In Springer Proceedings in Physics. Springer Singapore, 2016. http://dx.doi.org/10.1007/978-981-10-1926-5_122.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Reitsma, Frederik. "Pebble Bed Gas Cooled Reactors." In Encyclopedia of Nuclear Energy. Elsevier, 2021. http://dx.doi.org/10.1016/b978-0-12-819725-7.00188-4.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

DONNE, M. DALLE, U. FISCHER, G. SORDON, et al. "PEBBLE BED CANISTER: A CERAMIC BREEDER BLANKET WITH HELIUM COOLING FOR NET." In Fusion Technology 1986. Elsevier, 1986. http://dx.doi.org/10.1016/b978-1-4832-8376-0.50045-0.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Richrath, Marco, Sebastian Lohse, Marcus Grünewald, and David W. Agar. "Particle-scale heat removal in fixed-bed catalytic reactors: Modelling and optimisation of a desorptive cooling process." In Computer Aided Chemical Engineering. Elsevier, 2005. http://dx.doi.org/10.1016/s1570-7946(05)80234-2.

Full text
APA, Harvard, Vancouver, ISO, and other styles

Conference papers on the topic "Pebble bed reactors – Cooling"

1

Zhao, Xiang, Trent Montgomery, and Sijun Zhang. "Combined CFD and DEM Simulations of Fluid Flow and Heat Transfer in a Pebble Bed Reactor." In ASME 2011 Small Modular Reactors Symposium. ASMEDC, 2011. http://dx.doi.org/10.1115/smr2011-6517.

Full text
Abstract:
This paper presents combined computational fluid dynamics (CFD) and discrete element method (DEM) simulations of fluid flow and relevant heat transfer in the pebble bed reactor core. In the pebble bed reactor core, the coolant passes highly complicated flow channels, which are formed by thousands of pebbles in a random way. The random packing structure of pebbles is crucial to CFD simulations results. The realistic packing structure in an entire pebble bed reactor (PBR) is generated by discrete element method (DEM). While in CFD calculations, selection of the turbulence models have great impor
APA, Harvard, Vancouver, ISO, and other styles
2

Cogliati, Joshua J., and Abderrafi M. Ougouag. "Pebble Bed Reactor Dust Production Model." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58289.

Full text
Abstract:
The operation of pebble bed reactors, including fuel circulation, can generate graphite dust, which in turn could be a concern for internal components; and to the near field in the remote event of a break in the coolant circuits. The design of the reactor system must, therefore, take the dust into account and the operation must include contingencies for dust removal and for mitigation of potential releases. Such planning requires a proper assessment of the dust inventory. This paper presents a predictive model of dust generation in an operating pebble bed with recirculating fuel. In this preli
APA, Harvard, Vancouver, ISO, and other styles
3

Boer, B., J. L. Kloosterman, D. Lathouwers, T. H. J. J. van der Hagen, and H. van Dam. "Optimization of a Radially Cooled Pebble Bed Reactor." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58117.

Full text
Abstract:
By altering the coolant flow direction in a pebble bed reactor from axial to radial, the pressure drop can be reduced tremendously. In this case the coolant flows from the outer reflector through the pebble bed and finally to flow paths in the inner reflector. As a consequence, the fuel temperatures are elevated due to the reduced heat transfer of the coolant. However, the power profile and pebble size in a radially cooled pebble bed reactor can be optimized to achieve lower fuel temperatures than current axially cooled designs, while the low pressure drop can be maintained. The radial power p
APA, Harvard, Vancouver, ISO, and other styles
4

Serfontein, Dawid, Eben Mulder, and Eberhard Teuchert. "Proposal for an International Experimental Pebble Bed Reactor." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58174.

Full text
Abstract:
HTRs, both prismatic block fuelled and pebble fuelled, feature a number of uniquely beneficial characteristics that will be discussed in this paper. In this paper the construction of an international experimental pebble bed reactor is proposed, possible experiments suggested and an invitation extended to interested partners for co-operation in the project. Experimental verification by nuclear regulators in order to facilitate licensing and the development of a new generation of reactors create a strong need for such a reactor. Suggested experiments include: • Optimized incineration of waste Pu
APA, Harvard, Vancouver, ISO, and other styles
5

Yu, Xinli, and Suyuan Yu. "The Gasification of Graphite Matrix in Pebble Bed Reactors." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75827.

Full text
Abstract:
This paper mainly deals with the simulations of graphite matrix of the spherical fuel elements by steam in normal operating conditions. The fuel element matrix graphite was firstly simplified to an annular part in the simulations. Then the corrosions to the matrix graphite in 10 MW High Temperature Gas-cooled Reactor (HTR-10) and the High Temperature Gas-cooled Reactor—–Pebble-bed Module (HTR-PM) were investigated respectively. The results showed that the gasification of fuel element matrix graphite was uniform and mainly occurred at the bottom of the core in both of the reactors in the mean r
APA, Harvard, Vancouver, ISO, and other styles
6

Troshko, Andrey A., and Ajey Y. Walavalkar. "Simulation of Multiphase Heat Transfer in Pebble Bed Modular Reactor." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49089.

Full text
Abstract:
Computational Fluid Dynamics in conjunction with an Eulerian multiphase model of heat transfer in a Pebble Bed Modular Reactor (PBMR) was validated against experimental data obtained in a test rig. The cooling gas and packed fuel pebbles constituted two phases. The velocity of pebble phase was fixed to zero and a drag law accounting for a packed bed condition was used. The density of the gas phase varied with temperature. Volume averaged effective thermal conductivities accounting for radiation and packed spheres geometry were used for both phases. Model predictions compared favorably with the
APA, Harvard, Vancouver, ISO, and other styles
7

Liu, Limin, Dalin Zhang, Linfeng Li, Yichen Yang, Chenglong Wang, and Suizheng Qiu. "Experimental Studies on the Thermal-Hydraulics of Dowtherm A Through the Pebble Bed With Internal Heat Generation." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81917.

Full text
Abstract:
The Fluoride-salt-cooled High temperature Reactors (FHRs) are an advanced concept using a novel combination of high-temperature coated-particle fuel, low-pressure fluoride-salt coolant and air-Brayton power conversion system. Prismatic fuel or pebble fuel are adopted for the conceptual core designs of FHRs like TMSR-SF, MK1 PB-FHR and SM-AHTR. The high-Prandtl-number FLiBe is mainly adopted as the primary coolant, which specifies in high melting and boiling point and high volumetric capacity. The experimental results obtained from the air, water or inert gas prove reliable for the Prandtl numb
APA, Harvard, Vancouver, ISO, and other styles
8

Tsiklauri, G., D. Newman, G. Meriwether, and V. Korolev. "Pebble Bed Boiling Water Reactor Concept With Superheated Steam." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22045.

Full text
Abstract:
An Advanced Nuclear Reactor concept is presented which extends Boiling Water Reactor technology with micro-fuel elements (MFE) and produces superheated steam. A nuclear plant with MFE is highly efficient and safe, due to ceramic-clad nuclear fuel. Water is used as both moderator and coolant. The fuel consists of spheres of about 1.5 mm diameter of UO2 with several external coatings of different carbonaceous materials. The outer coating of the particles is SiC, manufactured with chemical vapor disposition (CVD) technology. Endurance of the integrity of the SiC coating in water, air and steam ha
APA, Harvard, Vancouver, ISO, and other styles
9

Fick, Lambert, Elia Merzari, and Yassin Hassan. "Direct Numerical Simulation of the Flow Through a Structured Pebble Bed Near a Wall Boundary." In ASME/JSME/KSME 2015 Joint Fluids Engineering Conference. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/ajkfluids2015-3701.

Full text
Abstract:
Packed pebble beds occur in many industrial applications, including the very high temperature and molten salt nuclear reactor design concepts. These designs are currently being researched as possible fourth-generation nuclear power system designs. In order to ensure proper cooling of the reactor cores in these systems during normal operation, as well as under accident conditions, a detailed understanding of the coolant flow behavior is required. Direct numerical simulation (DNS) can be used to simulate specific pebble bed flow and geometry conditions in order to develop high-fidelity fluid flo
APA, Harvard, Vancouver, ISO, and other styles
10

Zhao, Gang, Ping Ye, and Toru Obala. "Variant Porosity Pebble Bed Reactor Core Thermal Hydraulic Simulation." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29125.

Full text
Abstract:
Spherical fuel elements are distributed randomly in the pebble bed reactor core and helium flow through the pebble bed to remove nuclear reaction heat. Pebble bed reactor core is usually treated as a uniform porous media flow in thermal hydraulic research. However the porosity distribution is nonuniform and the porosity near the wall increase sharply. A new random model is developed in this paper to investigate thermal hydraulic characteristics of pebble bed reactor core. Porosity assumption is based on porosity measurement of other research. Porosity simulation is divided into three parts acc
APA, Harvard, Vancouver, ISO, and other styles

Reports on the topic "Pebble bed reactors – Cooling"

1

Kovacic, Donald N., Philip Gibbs, and Logan Scott. Model MC&A for Pebble Bed Reactors. Office of Scientific and Technical Information (OSTI), 2020. http://dx.doi.org/10.2172/1606926.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Cui, Yonggang. Machine Learning in Safeguards at Pebble Bed Reactors. Office of Scientific and Technical Information (OSTI), 2020. http://dx.doi.org/10.2172/1679954.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Ugaz, Victor, Yassin Hassan, Thien Nguyen, and Elia Merzari. Experimental and Computational Analysis of NEAMS Pebble Bed Reactors. Office of Scientific and Technical Information (OSTI), 2019. http://dx.doi.org/10.2172/1580655.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Hans D. Gougar, Abderrafi M. Ougouag, and William K. Terry. Advanced Core Design And Fuel Management For Pebble-Bed Reactors. Office of Scientific and Technical Information (OSTI), 2004. http://dx.doi.org/10.2172/911213.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Sen, Sonat. Benchmark for Fuel Shuffling and Depletion for Pebble Bed Reactors. Office of Scientific and Technical Information (OSTI), 2020. http://dx.doi.org/10.2172/1708878.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Zou, Ling, Dan O'Grady, Guojun Hu, and Rui Hu. Explicit Modeling of Pebble Temperature in the Porous-medium Framework for Pebble-bed Reactors Applications. Office of Scientific and Technical Information (OSTI), 2021. http://dx.doi.org/10.2172/1773605.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Forsberg, Charles W., and David Lewis Moses. Safeguards Challenges for Pebble-Bed Reactors (PBRs):Peoples Republic of China (PRC). Office of Scientific and Technical Information (OSTI), 2009. http://dx.doi.org/10.2172/969660.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Mui, Travis, Ishak Johnson, Ling Zou, and Rui Hu. Improvements of SAM Heat Transfer Models for Molten Salt-Cooled Pebble Bed Reactors. Office of Scientific and Technical Information (OSTI), 2021. http://dx.doi.org/10.2172/1808874.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Skutnik, Steve, and William Wieselquist. Assessment of ORIGEN Reactor Library Development for Pebble-Bed Reactors Based on the PBMR-400 Benchmark. Office of Scientific and Technical Information (OSTI), 2021. http://dx.doi.org/10.2172/1807271.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Brian Boer and Abderrafi M. Ougouag. Final Report on Utilization of TRU TRISO Fuel as Applied to HTR Systems Part I: Pebble Bed Reactors. Office of Scientific and Technical Information (OSTI), 2011. http://dx.doi.org/10.2172/1013722.

Full text
APA, Harvard, Vancouver, ISO, and other styles
You might also be interested in the extended bibliographies on the topic 'Pebble bed reactors – Cooling' for particular source types:
Journal articles Dissertations / Theses
We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!

To the bibliography