15 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Pyrolytic Carbon"  
Results: 1 - 15
open access

RESULTS OF TESTS TO DEMONSTRATE A SIX-INCH-DIAMETER COATER FOR PRODUCTION OF TRISO-COATED PARTICLES FOR ADVANCED GAS REACTOR EXPERIMENTS

Description: The Next Generation Nuclear Plant (NGNP)/Advanced Gas Reactor (AGR) Fuel Development and Qualification Program includes a series of irradiation experiments in Idaho National Laboratory’s (INL’s) Advanced Test Reactor. TRISOcoated particles for the first AGR experiment, AGR-1, were produced at Oak Ridge National Laboratory (ORNL) in a two inch diameter coater. A requirement of the NGNP/AGR Program is to produce coated particles for later experiments in coaters more representative of industrial s… more
Date: September 1, 2008
Creator: Barnes, Charles M
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Sound velocity of carbon at high pressures

Description: We have measured the sound velocity in shock compressed graphite. The data are consistent with a model of solid diamond from 0.8 to 1.4 Mbar. 18 references.
Date: September 11, 1984
Creator: Shaner, J. W.; Brown, J. M.; Swenson, C. A. & McQueen, R. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Effects of deposition conditions on the properties of pyrolytic carbon deposited in a fluidized bed

Description: The high-density, isotropic pyrolytic carbon layer beneath the silicon carbide (IPyC) plays a key role in the irradiation performance of coated particle fuel. The IPyC layer protects the kernel from reactions with chlorine during deposition of the SiC layer, provides structural support for the SiC layer, and protects the SiC from fission products and carbon monoxide. The process conditions used by the Germans to deposit the IPyC coating produced a highly isotropic, but somewhat permeable IPyC c… more
Date: September 1, 2005
Creator: Lowden, Richard Andrew; Hunn, John D; Nunn, Stephen D; Kercher, Andrew K; Price, Jeffery R & Jellison Jr, Gerald Earle
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PARFUME Theory and Model basis Report

Description: The success of gas reactors depends upon the safety and quality of the coated particle fuel. The fuel performance modeling code PARFUME simulates the mechanical, thermal and physico-chemical behavior of fuel particles during irradiation. This report documents the theory and material properties behind vari¬ous capabilities of the code, which include: 1) various options for calculating CO production and fission product gas release, 2) an analytical solution for stresses in the coating layers that… more
Date: September 1, 2009
Creator: Knudson, Darrell L.; Miller, Gregory K; Miller, G. K.; Petti, D. A.; Maki, J. T. & Knudson, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Codisposal Viability for TH/U Carbide (Fort Saint Vrain HTGR) DOE-Owned Fuel

Description: There are more than 250 forms of US Department of Energy (DOE)-owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The Fort Saint Vrain reactor (FSVR) SNF has been designated as the representative fuel for the Th/U carbide fuel group. The FSVR SNF consists of small particles (spheres of t… more
Date: September 28, 2001
Creator: Radulescu, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pyrographite Water-Cooled Target Analysis

Description: This report presents a study of two pyrographic water-cooled targets planned for use in the Clinton P. Anderson Meson Physics Facility. A steady-state thermal stress analysis was done that included a parameter study on the physical and numerical variables that affect the problem. The maximum target temperatures and stresses were calculated and compared for a variety of conditions. The comparisons show that the 0.6-cm half-width fin target proposed for the A-2 line is the most vulnerable of the … more
Date: September 1, 1980
Creator: Bennett, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Multibarrier waste forms. Part I. Development

Description: The multibarrier concept produces a composite waste form with enhanced inertness through improvements in thermal stability, mechanical strength, and leachability by the use of coatings and metal matrices. This report describes research and development activities resulting in the demonstration of the multibarrier concept for nonradioactive simulated waste compositions. The multibarrier concept is to utilize up to three barriers to isolate radionuclides from the environment: a solid waste inner c… more
Date: September 1, 1978
Creator: Rusin, J.M.; Lokken, R.O.; Lukacs, J.M.; Sump, K.R.; Browning, M.F. & McCarthy, G.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Helium generation and diffusion in graphite and some carbides. [14. 9 and 14. 4 MeV neutrons]

Description: The cross section for the generation of helium in neutron irradiated carbon was found to be 654 mb at 14.4 MeV and 744 mb at 14.9 MeV. Extrapolating to 14.1 MeV (the fusion reactor spectrum) gives 615 mb. The diffusion of helium in dense polycrystalline graphite and in pyrographite was measured and found to be D = 7.2 x 10/sup -7/ m/sup 2/s/sup -1/ exp (-80 kJ/RT). It is assumed that diffusion is primarily in the basal plane direction in crystals of the graphite. In polycrystalline graphite the… more
Date: September 17, 1976
Creator: Holt, J. B.; Guinan, M. W.; Hosmer, D. W.; Condit, R. H. & Borg, R. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Material Performance of Fully-Ceramic Micro-Encapsulated Fuel under Selected LWR Design Basis Scenarios: Final Report

Description: The extension to LWRs of the use of Deep-Burn coated particle fuel envisaged for HTRs has been investigated. TRISO coated fuel particles are used in Fully-Ceramic Microencapsulated (FCM) fuel within a SiC matrix rather than the graphite of HTRs. TRISO particles are well characterized for uranium-fueled HTRs. However, operating conditions of LWRs are different from those of HTRs (temperature, neutron energy spectrum, fast fluence levels, power density). Furthermore, the time scales of transient … more
Date: September 1, 2011
Creator: Boer, B.; Sen, R. S.; Pope, M. A. & Ougouag, A. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

RESULTS OF TESTS TO DEMONSTRATE A SIX-INCH DIAMETER COATER FOR PRODUCTION OF TRISO-COATED PARTICLES FOR ADVANCED GAS REACTOR EXPERIMENTS

Description: The Next Generation Nuclear Plant (NGNP)/Advanced Gas Reactor (AGR) Fuel Development and Qualification Program includes a series of irradiation experiments in Idaho National Laboratory's (INL's) Advanced Test Reactor. TRISOcoated particles for the first AGR experiment, AGR-1, were produced at Oak Ridge National Laboratory (ORNL) in a twoinch diameter coater. A requirement of the NGNP/AGR Program is to produce coated particles for later experiments in coaters more representative of industrial sc… more
Date: September 1, 2008
Creator: Marshall, Douglas W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Raman spectroscopy of C-irradiated graphite

Description: Highly oriented pyrolytic graphite samples were irradiated with C{sup +} ions at 35 keV in a direction normal to the basal plane and subsequently annealed up to 1373 K. Substantial surface topography changes were observed at fluences of 5 {times} 10{sup 18} ions/m{sup 2} and higher using scanning electron and atomic force microscopies. Intricate networks of surface cracks and ridges developed after high dose implantation. A systematic study of the irradiation effects was conducted using Raman s… more
Date: September 1, 1994
Creator: Hembree, D. M. Jr.; Pedraza, D. F.; Romanoski, G. R.; Withrow, S. P. & Annis, B. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Size effect on the irradiation performance of coated fuel particles

Description: Outer coatings that were as near alike as possible were applied to two different sizes of inert TRISO particles that were larger than those commonly used to fuel HTGR reactors, and these particles were then irradiated in a test reactor to observe the influence of particle size on outer coating failures that resulted from irradiation-induced shrinkage of coatings onto the more stable SiC substrates over which they were applied. Outer coatings of plain pyrocarbon and of Si-alloyed pyrocarbon were… more
Date: September 1, 1980
Creator: Bullock, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
Back to Top of Screen