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Fission Product Sic Reaction In Htgr Fuel
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Book Synopsis Fission-product SiC Reaction in HTGR Fuel by :
Download or read book Fission-product SiC Reaction in HTGR Fuel written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The primary barrier to release of fission product from any of the fuel types into the primary circuit of the HTGR are the coatings on the fuel particles. Both pyrolytic carbon and silicon carbide coatings are very effective in retaining fission gases under normal operating conditions. One of the possible performance limitations which has been observed in irradiation tests of TRISO fuel is chemical interaction of the SiC layer with fission products. This reaction reduces the thickness of the SiC layer in TRISO particles and can lead to release of fission products from the particles if the SiC layer is completely penetrated. The experimental section of this report describes the results of work at General Atomic concerning the reaction of fission products with silicon carbide. The discussion section describes data obtained by various laboratories and includes (1) a description of the fission products which have been found to react with SiC; (2) a description of the kinetics of silicon carbide thinning caused by fission product reaction during out-of-pile thermal gradient heating and the application of these kinetics to in-pile irradiation; and (3) a comparison of silicon carbide thinning in LEU and HEU fuels.
Book Synopsis Simulated Fission Product-SiC Interaction in Triso-coated LEU Or MEU HTGR Fuel Particles by : R. L. Pearson
Download or read book Simulated Fission Product-SiC Interaction in Triso-coated LEU Or MEU HTGR Fuel Particles written by R. L. Pearson and published by . This book was released on 1980 with total page 71 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Behavior of Pyrolytic Silicon Carbide. [HTGR]. by :
Download or read book Irradiation Behavior of Pyrolytic Silicon Carbide. [HTGR]. written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fuel particles for the High-Temperature Gas-Cooled Reactor (HTGR) contain a layer of pyrolytic silicon carbide to act as a miniature pressure vessel and primary fission-product barrier. Optimization of the SiC with respect to fuel performance involves four areas of study: characterization of as-deposited SiC coatings; thermodynamics and kinetics of chemical reactions between SiC and fission products; irradiation behavior of SiC in the absence of fission products; and combined effects of irradiation and fission products. This paper reports the behavior of SiC deposited on inert microspheres and irradiated to fast-neutron fluences typical of HTGR fuel at end-of-life.
Book Synopsis Experiments on the Release of Fission Products from Molten Reactor Fuels by : G. E. Creek
Download or read book Experiments on the Release of Fission Products from Molten Reactor Fuels written by G. E. Creek and published by . This book was released on 1959 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission product behavior in HTGR fuel particles made from weak-acid resins by : T. N. Tiegs
Download or read book Fission product behavior in HTGR fuel particles made from weak-acid resins written by T. N. Tiegs and published by . This book was released on 1979 with total page 51 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Behavior of Fission Product Gases in HTGR Fuel Material by :
Download or read book Behavior of Fission Product Gases in HTGR Fuel Material written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This document is a status report on experimental data relating to the behavior of fission product gases in HTGR fuel material. It contains (1) a review of published experimental data on the behavior of gaseous fission products (noble gases, halogens, and related elements) in HTGR fuel materials and (2) new data on fission gas behavior. From the experimental data, the effects of fission product element, fuel configuration, nuclide half-life, temperature, pressure, neutron flux, neutron fluence, and fuel hydrolysis on fission gas release are deduced. Also on the basis of the experimental data, a model is formulated for the release of fission gases from fuel rods. The data presented in this report are being confirmed and extended through continuing work at General Atomic and other laboratories.
Book Synopsis Simulated Fission Product Oxide Behavior in Triso-coated HTGR Fuel by :
Download or read book Simulated Fission Product Oxide Behavior in Triso-coated HTGR Fuel written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Performance of Pyrolytic Silicon Carbide Coatings on Fissile Fuel Particles by :
Download or read book Irradiation Performance of Pyrolytic Silicon Carbide Coatings on Fissile Fuel Particles written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fuel particles for the High Temperature Gas-Cooled Reactor (HTGR) contain a layer of pyrolytic silicon carbide to act as a miniature pressure vessel and primary fission product barrier. Optimization of the SiC coating with respect to fuel performance involves four areas of study: (a) characterization of as-deposited SiC coatings; (b) thermodynamics and kinetics of chemical reactions between SiC and fission products; (c) irradiation behavior of SiC in the absence of fission products; and (d) the combined effects of irradiation and fission product interactions. This paper reports the behavior of SiC deposited on fissile fuel particles and irradiated to fast neutron fluences typical of HTGR fuel at end-of-life.
Book Synopsis Measurement and Modelling of Postirradiation Fission Product Release from HTGR Fuel Particles Under Accident Conditions by :
Download or read book Measurement and Modelling of Postirradiation Fission Product Release from HTGR Fuel Particles Under Accident Conditions written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A study was performed to provide a description of the release of fission products from failed fuel particles during a core heatup event in an HTGR. The need for this study was established in the Accident Initiation and Progression Analysis program. The release of fission products was measured from laser-failed BISO ThO2, TRISO UC2, and weak acid resin (WAR) particles over a range of burnups. The burnups were 0.25, 1.4 and 15.7% FIMA for ThO2 particles, 23.5 and 74% FIMA for UC2 particles, and 60% FIMA for WAR particles. The fission products measured were nuclides of xenon, iodine, krypton, tellurium, and cesium. Two types of experiments were performed: isothermal and temperature rise experiments. The range of the temperatures was from 1200° to 2300°C. In the temperature rise experiments, the heating rates were between 50° and 450°C/h.
Book Synopsis Fission product Pd-SiC interaction in irradiated coated fuel particles by : T. N. Tiegs
Download or read book Fission product Pd-SiC interaction in irradiated coated fuel particles written by T. N. Tiegs and published by . This book was released on 1980 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Modeling of Fission Product Release from HTR (high Temperature Reactor) Fuel for Risk Analyses by :
Download or read book Modeling of Fission Product Release from HTR (high Temperature Reactor) Fuel for Risk Analyses written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US and FRG have developed methodologies to determine the performance of and fission product release from TRISO-coated fuel particles under postulated accident conditions. The paper presents a qualitative and quantitative comparison of US and FRG models. The models are those used by General Atomics (GA) and by the German Nuclear Research Center at Juelich (KFA/ISF). A benchmark calculation was performed for fuel temperatures predicted for the US Department of Energy sponsored Modular High Temperature Gas Cooled Reactor (MHTGR). Good agreement in the benchmark calculations supports the on-going efforts to verify and validate the independently developed codes of GA and KFA/ISF. This work was performed under the US/FRG Umbrella Agreement for Cooperation on Gas Cooled Reactor Development. 6 refs., 3 figs., 3 tabs.
Book Synopsis The Measurement and Modelling of Postirradiation Fission Product Release from HTGR Fuel Particles Under Accident Conditions by :
Download or read book The Measurement and Modelling of Postirradiation Fission Product Release from HTGR Fuel Particles Under Accident Conditions written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Licensing Topical Report written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The release of fission products from failed fuel particles was measured under simulated accident (core heatup) conditions. A generic model and specific model parameters that describe delayed fission product release from the kernels of failed HTGR fuel particles were developed from the experimental results. The release of fission products was measured from laser-failed BISO ThO2 and highly enriched (HEU) TRISO UC2 particles that had been irradiated to a range of kernel burnups. The burnups were 0.25, 1.4, and 15.7% FIMA for ThO2 particles and 23.5 and 74% FIMA for UC2 particles. The fission products measured were nuclides of xenon, iodine, krypton, tellurium, and cesium.
Book Synopsis Fission Product Control in HTGR Plants by :
Download or read book Fission Product Control in HTGR Plants written by and published by . This book was released on 1974 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A STUDY OF FISSION PRODUCT TRANSPORT MECHANISMS IN HIGH TEMPERATURE GAS- COOLED REACTOR FUEL ELEMENTS. by :
Download or read book A STUDY OF FISSION PRODUCT TRANSPORT MECHANISMS IN HIGH TEMPERATURE GAS- COOLED REACTOR FUEL ELEMENTS. written by and published by . This book was released on 1961 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The experimental work on the diffusion of fission products in graphite matrices at high temperatures is reviewed and the possible mechanisms of mass transport are discussed. Preliminary data are given on diffusion in these systems. It is shown that the rates of diffusion for fission products introduced by a recoil process into the moderatcr lattice can be correlated based on a random wahk solid state diffusion model. An expression is derived for the coefficient of diffusion in terms of the lattice parameters giving the coefficients of diffusion for different atomic species as an exponential function of the atomic radii. The possibility of other controlling mechanisms above 1000 deg C and the effect of carbide formation and other reactions is evaluated. (auth).
Book Synopsis Gaseous Fission Product Release During Storage at Various Temperatures for HTGR-type Fuels by : C. L. Fitzgerald
Download or read book Gaseous Fission Product Release During Storage at Various Temperatures for HTGR-type Fuels written by C. L. Fitzgerald and published by . This book was released on 1978 with total page 37 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Interaction of Noble-metal Fission Products with Pyrolytic Silicon Carbide by :
Download or read book Interaction of Noble-metal Fission Products with Pyrolytic Silicon Carbide written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fuel particles for the High-Temperature Gas-Cooled Reactor (HTGR) contain layers of pyrolytic carbon and silicon carbide, which act as a miniature pressure vessel and form the primary fission product barrier. Of the many fission products formed during irradiation, the noble metals are of particular interest because they interact significantly with the SiC layer and their concentrations are somewhat higher in the low-enriched uranium fuels currently under consideration. To study fission product-SiC interactions, particles of UO2 or UC2 are doped with fission product elements before coating and are then held in a thermal gradient up to several thousand hours. Examination of the SiC coatings by TEM-AEM after annealing shows that silver behaves differently from the palladium group.
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