Laboratory for Characterization of Irradiated Graphite
Abstract
The newly completed Idaho National Laboratory (INL) Carbon Characterization Laboratory (CCL) is located in Labs C19 and C20 of the Idaho National Laboratory Research Center (IRC). The CCL was established under the Next Generation Nuclear Plant (NGNP) Project to support graphite and ceramic composite research and development activities. The research is in support of the Advanced Graphite Creep (AGC) experiment — a major material irradiation experiment within the NGNP Graphite program. The CCL is designed to characterize and test low activated irradiated materials such as high purity graphite, carbon-carbon composites, and silicon-carbide composite materials. The laboratory is fully capable of characterizing material properties for both irradiated and nonirradiated materials.
- Authors:
- Publication Date:
- Research Org.:
- Idaho National Laboratory (INL)
- Sponsoring Org.:
- DOE - NE
- OSTI Identifier:
- 980792
- Report Number(s):
- INL/EXT-10-18039
TRN: US201012%%1215
- DOE Contract Number:
- DE-AC07-05ID14517
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CARBON; CERAMICS; COMPOSITE MATERIALS; GRAPHITE; IMPURITIES; IRRADIATION; MATERIALS; SUPPORTS; Carbon Characterization Laboratory; material irradiation experiment; NGNP
Citation Formats
Karen A. Moore. Laboratory for Characterization of Irradiated Graphite. United States: N. p., 2010.
Web. doi:10.2172/980792.
Karen A. Moore. Laboratory for Characterization of Irradiated Graphite. United States. doi:10.2172/980792.
Karen A. Moore. Mon .
"Laboratory for Characterization of Irradiated Graphite". United States.
doi:10.2172/980792. https://www.osti.gov/servlets/purl/980792.
@article{osti_980792,
title = {Laboratory for Characterization of Irradiated Graphite},
author = {Karen A. Moore},
abstractNote = {The newly completed Idaho National Laboratory (INL) Carbon Characterization Laboratory (CCL) is located in Labs C19 and C20 of the Idaho National Laboratory Research Center (IRC). The CCL was established under the Next Generation Nuclear Plant (NGNP) Project to support graphite and ceramic composite research and development activities. The research is in support of the Advanced Graphite Creep (AGC) experiment — a major material irradiation experiment within the NGNP Graphite program. The CCL is designed to characterize and test low activated irradiated materials such as high purity graphite, carbon-carbon composites, and silicon-carbide composite materials. The laboratory is fully capable of characterizing material properties for both irradiated and nonirradiated materials.},
doi = {10.2172/980792},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Mar 01 00:00:00 EST 2010},
month = {Mon Mar 01 00:00:00 EST 2010}
}
-
The Carbon Characterization Laboratory (CCL) is located in Labs C19 and C20 of the Idaho National Laboratory Research Center. The CCL was established under the Next Generation Nuclear Plant Project to support graphite and ceramic composite research and development activities. The research conducted in this laboratory will support the Advanced Graphite Creep experiments—a major series of material irradiation experiments within the Next Generation Nuclear Plant Graphite program. The CCL is designed to characterize and test low activated irradiated materials such as high purity graphite, carbon-carbon composites, silicon-carbide composite, and ceramic materials. The laboratory is fully capable of characterizing material propertiesmore »
-
Conceptual Design Report for the Irradiated Materials Characterization Laboratory (IMCL)
This document describes the design at a conceptual level for the Irradiated Materials Characterization Laboratory (IMCL) to be located at the Materials and Fuels Complex (MFC) at the Idaho National Laboratory (INL). The IMCL is an 11,000-ft2, Hazard Category-2 nuclear facility that is designed for use as a state of the-art nuclear facility for the purpose of hands-on and remote handling, characterization, and examination of irradiated and nonirradiated nuclear material samples. The IMCL will accommodate a series of future, modular, and reconfigurable instrument enclosures or caves. To provide a bounding design basis envelope for the facility-provided space and infrastructure, anmore » -
Implementation Plan for the Irradiated Materials Characterization Laboratory (IMCL)
This document contains details regarding the planned implementation of the Irradiated Materials Characterization Laboratory at the INL. -
Development of an Apparatus for Measuring the Thermal Conductivity of Irradiated or Non-Irradiated Graphite; REALISATION D'UN APPAREIL DE MESURE DE LA CONDUCTIBILITE THERMIQUE DU GRAPHITE IRRADIE OU NON IRRADIE
An apparatus was developed for measuring the thermal conductivity coefficient K of irradiated or nonirradiated graphite. The measurement of K at around room temperature with an accuracy of about 5% is possible. The study specimen is placed in a vacuum between a hot and a cold source which create a temperature gradient DELTA be- / DELTA x in the steady state. The amount of heat transferred, Q, is deduced from the electrical power dissipated at the hot source, after allowing for heat losses. The thermal conductivity coefficient is defined as: K = Q/S. DELTA x/ DELTA be- , S beingmore » -
DIMENSIONAL CHANGES OF GRAPHITE SPECIMENS IRRADIATED IN DRAGON FUEL ELEMENT 700. PART II. SOME COMMENTS ON THE IRRADIATION SHRINKAGE OF GRAPHITE. Project DRAGON.
Although the qualitative mechanism of irradiation damage and dimensional change of graphite crystallites is quite well understood, the existing quantitative theories do not predict the irradiation shrinkage behaviour of a range of graphites with very good accuracy. It is suggested that this is because the effects of crystallite height, crystallite diameter crystallite shape and crystallite mechanical properties such as the shear modulus are not considered with respect to the magnitude of crystallite/crystallite dimensional interactions. A model which takes into account these effects is developed and the associated physical property parameter correlated against the initial irradiation volume shrinkage rates of fourteenmore »