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Saturday, November 14, 2020 | History

2 edition of Improved graphite matrix for coated-particle fuel found in the catalog.

Improved graphite matrix for coated-particle fuel

Donald H. Schell

Improved graphite matrix for coated-particle fuel

  • 330 Want to read
  • 26 Currently reading

Published by [Dept. of Energy], for sale by the National Technical Information Service] in Los Alamos, N.M, [Springfield, Va .
Written in English

    Subjects:
  • Nuclear fuel elements.,
  • Extrusion process.

  • Edition Notes

    StatementDonald H. Schell, Keith V. Davidson.
    SeriesLA ; 7423, LA (Series) (Los Alamos, N.M.) -- 7423.
    ContributionsDavidson, Keith V., Los Alamos Scientific Laboratory., United States. Dept. of Energy.
    The Physical Object
    Pagination14 p. :
    Number of Pages14
    ID Numbers
    Open LibraryOL17651122M

      Failed fuel to assess fission product retention and transport in reactor graphite and fuel matrix. Engineering scale particles in lab-scale compacts. Includes UCO and UO. 2. fuel. 5. AGR AGR AGR-3/4* AGR-5/6/7. Fuel Fabrication *Includes fabrication of DTF particles; driver fuel taken from AGR-1 fabrication campaign.   Walter H. Zinn Medal. Presented to William E. Burchill, ANS past president (–) and member since , retired Nuclear Engineering Department head at Texas A&M University, for major research contributions in materials corrosion and degradation processes in nuclear energy systems, and for impact on the nuclear industry through the development of improved fuel cladding .


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Improved graphite matrix for coated-particle fuel by Donald H. Schell Download PDF EPUB FB2

Get this from a library. Improved graphite matrix for coated-particle fuel. [Donald H Schell; Keith V Davidson; Los Alamos Scientific Laboratory.; United States. Department of Energy.]. Chapter Sixteen. Graphite-matrix Fuels Advanced Fuel-element Concepts Graphite as a Fuel Matrix Fuel-Graphite Geometries Fuel-element Fabrication Effect of Fuel Loading and Particle Size on Physical Properties Radiation Effects in Fueled Graphite Fission-product Release from Fueled GraphiteBook Edition: 1.

Whittaker, M P. Improved graphite systems for advanced fuel element States: N. p., Web. doi/   The inner zone contains about triple-coated isotropic fuel particles of μm in diameter dispersed in the graphite matrix.

The graphite matrix covers about 95% weight of the fuel element. Download: Download full-size image; Fig. Structures of the coated particle and fuel element of HTR in China: (A) cross-section of the coated Cited by:   There is the option of adopting closed fuel cycles.

Relative to light water reactor (LWR) spent nuclear fuel (SNF), all graphite-matrix coated-particle SNFs share the common characteristics of superior proliferation resistance and long-term performance as a waste form in a geological by: 5. Three dowel pins are installed on the top face, and they engage with dowel sockets in the bottom face of the block above.

TRISO-coated fuel particles with UO 2 kernel are dispersed in the graphite matrix and sintered to form a fuel compact. Fuel compacts are installed in a fuel rod made of graphite, 34 mm in outer diameter and mm in length.

The TRISO particles were overcoated prior to compacting with a resinated powder containing 64 wt% natural graphite, 16 wt% synthetic graphite, and 20 wt% thermosetting resin (Pappano et al., Graphite matrix material formulation Overcoating TRISO coated fuel particles Compact fabrication 6.

IN-CORE STRUCTURAL MATERIALS AND COMPONENTS Hexagonal block fuel elements for the prismatic HTGR design In-core graphitic materials In-core ceramic and ceramic composite materials 7. TRISO-COATED PARTICLE FUEL.

Journals & Books; Register Vol Issues 3–4,Pages Coated particle fuel to improve safety, design, economics in water-cooled and gas-cooled reactors. Author links open overlay panel J.

Porta a P. Lo Pinto Due to the use of SiC-coated graphite as fuel matrix and of an air/steam mixture as coolant the system has no. Tristructural Isotropic (TRISO) Coated Particle Fuel (OPyC) (IPyC) 12 mm. 25 mm. Spherical fuel pebbles. Prismatic graphite blocks. Cylindrical fuel compacts.

Pebble bed reactor. Prismatic reactor. Particle design provides excellent fission product retention in the fuel and is at the heart of the safety basis for high temperature gas reactors. Request PDF | Stress Analysis of Coated Particle Fuel in Graphite of High-Temperature Reactors | The PArticle STress Analysis (PASTA) code was written to evaluate stresses in coated particle fuel.

Studies of mechanical behaviour and fission gas release from coated particle fuel to high burn-up. Miniature high power density compacts.

Fission gas release behaviour of coated particle fuel at high burn-up and high fast neutron dose. A range of fuel types have been studied UC^, UO^ and Puminiature, high power density fuel bodies, bodies. This study aims to provide microstructural characterization for the matrix graphite which molten salt reactors (MSRs) use, and improve resistance to molten salt infiltration of the matrix graphite for fuel elements.

Mesocarbon microbeads (MCMB) densified matrix graphite A (MDG) was prepared by a quasi-isostatic pressure process.

After. This study aims to provide microstructural characterization for the matrix graphite which molten salt reactors (MSRs) use, and improve resistance to m. The total weight loss of HTGR graphite was %, graphite support was % at fuel temperature of °C with a delay of minutes and a pressurized time of minutes (Weight loss of.

This reactor was built but not tested, due to the cancellation of all work in this area in The goals of this experiment included testing of a novel coated particle fuel, using a graphite fuel matrix with a coefficient of thermal expansion closely matched to that of the coating, to reduce thermal stress and cracking.

NRX-A1 NRX-A2. The Fluoride-Salt-Cooled High-Temperature Reactor (FHR) is a new reactor concept that uses the graphite-matrix coated-particle fuel from gas-cooled reactors and a. Another type of graphite-encapsulated fuel and breeder element embodying the present invention is shown in FIG.

3 in which the element 40 can be seen to have a matrix of graphite in which the relatively large particles 10 with fertile-material kernels are distributed; between these partic the smaller particles 13 with fuel-containing.

Failed fuel to assess fission product retention and transport in reactor graphite and fuel matrix. Engineering-scale particles in lab-scale compacts. Includes UCO and UO. fuel. AGR AGR AGR-3/4* AGR-5/6/7.

Fuel. Fabrication *Includes fabrication of DTF particles; driver fuel taken from AGR-1 fabrication campaign. of possible particle fuel architectures have been considered, the most widely envisioned deployment of this technology is dispersion of TRISO particles in a graphite matrix for gas reactor applications[2].

Coated particle fuels such as TRISO appear to be a significant advancement compared to a simple monolithic pellet of UO 2. However, even. - In a strict sense the term inert matrix fuel (IMF) refers to any nuclear fuel containing a low activation matrix as carrier for the fissile material.

Since the early days of nuclear technology, this idea has been investigated, originally with the goal to improve fuel properties or to save uranium resources. However, currently, the term IMF is strongly associated with plutonium fuel that does.

Graphite-Matrix Coated-Particle Fuel Can Take Many Forms Pebble Bed. Dowel Pin Graphite Block Annular Coolant Channel Fuel Rod Fuel Handling Hole Dowel Socket 3 6 0 m m mm Prismatic Fuel Block Flat Fuel Plates in Hex Configuration Base Case.

Pebble bed Lower cost Easier refueling FHR smaller pebbles and higher power density. Therefore, the graphite matrix must meet the criteria of physical and chemical properties specified for PBR fuel.

This paper focuses on the purification of the Indonesian natural graphite by using. The AHTR fuel is a graphite-matrix coated-particle fuel, the type used in MHTGRs.

The coolant is a molten fluoride salt more» with a boiling point near deg. Because of this low-pressure liquid coolant, the types of passive safety systems proposed for liquid-metal reactors (such as the General Electric S-PRISM) can be used. The proposed AHTR uses coated-particle graphite-matrix fuel similar to that used in high-temperature gas-cooled reactors (HTGRs), such as the General Atomics gas turbine-modular helium reactor.

However, unlike the HTGRs, the AHTR uses a molten-salt coolant and a pool configuration, similar to that of the General Electric Super Power Reactor. • Coated-particle graphite-matrix fuel developed for high-temperature gas-cooled reactors [3] in the United States and Germany, starting in the s.

• Passive safety systems for gas-cooled and liquid-metal reactors introduced in the s. • Advanced gas turbines—including commercialization in the last 5 years of magnetic bearing. The AHTR fuel is a graphite-matrix coated-particle fuel, the type used in MHTGRs. The coolant is a molten fluoride salt more» with a boiling point near deg.

Because of this low-pressure liquid coolant, the types of passive safety systems proposed for liquid-metal reactors (such as the General Electric S-PRISM) can be used.

A fuel assembly design concept with new fuel pellets was introduced and its nuclear feasibility on PWR application was shown in Ref. 1 under limited conditions. In this paper, a full-core analysis was performed for a partly loaded core with carbon-coated particle fuel assemblies.

The fluoride salt–cooled high-temperature reactor (FHR) uses clean fluoride salt coolants and the same graphite-matrix coated-particle fuel as high-temperature gas-cooled reactors.

Molten salt reactors (MSRs) dissolve the fuel in a fluoride or chloride salt with release of fission product tritium into the salt.

15 Metal matrix dispersion fuels • Benefits – Large database on similar fuels • Research reactor fuel, early R&D on steel matrix – Low failure consequence – Cold fuel - can operate at high power density if required – Fabrication of pins uses fast, simple technique (extrusion) – Should be capable of very high burnup • Issues – No data on Zr matrix fuel, experimental work required.

(LWRs). The fuel is the graphite-matrix coated-particle fuel used by high-temperature gas-cooled reactors (HTGRs) resulting in similar reactor core and fuel cycle designs—except the power density is greater because liquids are better coolants than gases.

The coolant is a. Tristructural isotropic (TRISO) coated particle fuel is a robust, microencapsulated fuel form developed originally for use in high-temperature gas-cooled reactors (HTGRs). The particles consist of a spherical fissile kernel surrounded by several layers of pyrocarbon and a silicon carbide (SiC) layer.

@article{osti_, title = {Integration of TRISO Fuel with Open-Cell Foam for Increased Performance and Manufacturability}, author = {Williams, Brian E. and Youchison, Dennis L.}, abstractNote = {Tristructural isotropic (TRISO) fuel is a key component of advanced small modular nuclear reactors due to its inherent safety at high temperatures and irradiation levels and decreased.

Designed-to-fail (DTF) fuel to assess fission product retention and transport in reactor graphite and fuel matrix. Engineering-scale particles in lab-scale compacts. Includes UCO and UO. fuel. AGR AGR AGR-3/4* AGR-5/6/7. Fuel. Fabrication *Includes fabrication of DTF particles; driver fuel taken from AGR -1 fabrication campaign.

Temperature Reactors (FHRs) with solid fuel and liquid salt coolants, (2) Molten Salt Reactors (MSRs) with fuel dissolved in the salt coolant, and (3) high-magnetic-field fusion machines with immersion salt coolant blankets.

The FHR is enabled by improved graphite-matrix coated-particle fuel developed for high-temperature gas-cooled. To characterize the fuel quality, the fraction of the defec- tive Sic coating layer of the as-manufactured fuels are measured by the burn-leach method.

In this method, the fuel compact or the coated fuel particles are heated at 1,K in air to oxidize the graphite matrix of the compact and the OPyC layers, followed by the acid 1. The problem set associated with the heat transfer from the fuel stick to the coolant gas in the HTGR is illustrated in Fig.

1 where the radial temperature drop is traced from the fuel stick centerline to the coolant gas. In detail, in the HTGR the coated particle fuel is embedded in a carbon matrix in the form of cylindrical fuel sticks.

AGR-3/4: This experiment was dedicated to studying fission product transport in fuel compact matrix material and reactor-grade graphite. This was accomplished by fabricating fuel compacts in which approximately 1 percent of the particles were “designed to fail” (DTF).

Performance of coated particle fuel in High Temperature Reactors Calculation procedure in stress analysis Derivation of an analytical model for a 4-layer pressure vessel Stress effects in the graphite matrix Stress analysis of coated particle fuel in current and future HTRs.

The HTR distinguishes itself from the other thermal reactors by the different fuel concept; the fuel is in the form of small particles ( |im diameter) of oxide or carbide fissile/fertile material coated by ceramic layers of PyC and eventually SiC; these particles are embedded in a graphite matrix whose disposition differs in the various.

The Fluoride-salt-cooled High-temperature Reactor (FHR) uses the same graphite-matrix coated-particle fuel as high-temperature gas-cooled reactors and clean fluoride salt coolants. Molten salt reactors (MSRs) dissolve the fuel in a fluoride or chloride .high-temperature creep.

Thus, the matrix is typi-cally the weak link in the PMC structure. The matrix phase of commercial PMCs can be classified as either thermoset or thermoplastic. The general characteristics of each matrix type are shown in figure ; however, recently de-veloped matrix resins have begun to change this picture, as noted below.

It combines high-temperature graphite-matrix coated particle fuel developed for high-temperature gas-cooled reactors (fuel failure temperature greater than °C), liquid salt developed for the molten salt reactors (boiling point greater than °C).