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Title: Irradiation High Heat Flux Synergism in Silicon Carbide-Based Fuel Claddings for Light Water Reactors

Authors:
 [1];  [1];  [1];  [1];  [1];  [2];  [3]
  1. ORNL
  2. Massachusetts Institute of Technology (MIT)
  3. General Atomics
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1341556
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: Top Fuel 2016 - Light Water Reactor (LWR) Fuel Performance Meeting, Boise, ID, USA, 20160911, 20160916
Country of Publication:
United States
Language:
English

Citation Formats

Katoh, Yutai, Terrani, Kurt A, Koyanagi, Takaaki, Petrie, Christian M, Singh, Gyanender P, Snead, Lance L, and Deck, Christian P. Irradiation High Heat Flux Synergism in Silicon Carbide-Based Fuel Claddings for Light Water Reactors. United States: N. p., 2017. Web.
Katoh, Yutai, Terrani, Kurt A, Koyanagi, Takaaki, Petrie, Christian M, Singh, Gyanender P, Snead, Lance L, & Deck, Christian P. Irradiation High Heat Flux Synergism in Silicon Carbide-Based Fuel Claddings for Light Water Reactors. United States.
Katoh, Yutai, Terrani, Kurt A, Koyanagi, Takaaki, Petrie, Christian M, Singh, Gyanender P, Snead, Lance L, and Deck, Christian P. Sun . "Irradiation High Heat Flux Synergism in Silicon Carbide-Based Fuel Claddings for Light Water Reactors". United States. doi:.
@article{osti_1341556,
title = {Irradiation High Heat Flux Synergism in Silicon Carbide-Based Fuel Claddings for Light Water Reactors},
author = {Katoh, Yutai and Terrani, Kurt A and Koyanagi, Takaaki and Petrie, Christian M and Singh, Gyanender P and Snead, Lance L and Deck, Christian P},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 2017},
month = {Sun Jan 01 00:00:00 EST 2017}
}

Conference:
Other availability
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  • The objective of volume 1 of this project was to determine the normal, spectral emittance of alpha-SiC (Hexoloy SA) and TiB2 toughened SiC (Hexoloy ST) in the mid-infrared at elevated temperatures. A two part literature survey is presented. The first part reviews the instrumentation required in emittance measurement techniques while the second part deals with the different techniques of measurement. A high-temperature emissometer based on the integral blackbody emission technique was designed, manufactured and assembled. The surface morphology and composition of the materials were characterized by scanning electron microscope and X-ray diffraction techniques, respectively.
  • High Flux Particle Bed Reactor (HFPBR) designs based on High Temperature Gas Reactors (HTGR) particular fuel are described. The coated fuel particles, approx.500 microns in diameter, are packed between porous metal frits, and directly cooled by flowing D/sub 2/O. The large heat transfer surface area in the packed bed, approx.100 cm/sup 2//cm/sup 3/ of volume, allows high power densities, typically 10 MW/liter. Peak thermal fluxes in the HFPBR are 1 to 2 x 1/sup 16/ n/c/sup 2/ sec., depending on configuration and moderator choice with beryllium and D/sub 2/O Moderators yielding the best flux performance. Spent fuel particles can bemore » hydraulically unloaded every day or two and fresh fuel reloaded. The short fuel cycle allows HFPBR fuel loading to be very low, approx.2 kg of /sup 235/U, with a fission product inventory one-tenth of that in present high flux research reactors. The HFPBR can use partially enriched fuel, 20% /sup 235/U, without degradation in flux reactivity. 8 refs., 12 figs., 2 tabs.« less
  • Development of silicon carbide (SiC) joints that retain adequate structural and functional properties in the anticipated service conditions is a critical milestone toward establishment of advanced SiC composite technology for the accident-tolerant light water reactor (LWR) fuels and core structures. Neutron irradiation is among the most critical factors that define the harsh service condition of LWR fuel during the normal operation. The overarching goal of the present joining and irradiation studies is to establish technologies for joining SiC-based materials for use as the LWR fuel cladding. The purpose of this work is to fabricate SiC joint specimens, characterize those jointsmore » in an unirradiated condition, and prepare rabbit capsules for neutron irradiation study on the fabricated specimens in the High Flux Isotope Reactor (HFIR). Torsional shear test specimens of chemically vapor-deposited SiC were prepared by seven different joining methods either at Oak Ridge National Laboratory or by industrial partners. The joint test specimens were characterized for shear strength and microstructures in an unirradiated condition. Rabbit irradiation capsules were designed and fabricated for neutron irradiation of these joint specimens at an LWR-relevant temperature. These rabbit capsules, already started irradiation in HFIR, are scheduled to complete irradiation to an LWR-relevant dose level in early 2015.« less