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Title: XRD and SANS evaluation of HOPG and Polycrystalline Graphite

Abstract

As the primary construction material used in gas-cooled reactor cores, either of high-temperature (HTR) or very high-temperature (VHTR) design, nuclear graphite must be well characterized and variations in its properties upon high-energy neutron irradiation must be known, understood, and predict ed as accurately as possible before a reactor is built and operational. However, even after more than 70 years of operation of graphite-moderated reactors and intense research on graphite’s behavior in an extreme environment created by high temperatures, irradiation, mechanical stress, and chemically reactive (oxidizing) gaseous environment, questions still remain.

Authors:
 [1];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1458356
Report Number(s):
ORNL/TM-2018/871
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Gallego, Nidia C., Contescu, Cristian I., and Burchell, Timothy D. XRD and SANS evaluation of HOPG and Polycrystalline Graphite. United States: N. p., 2018. Web. doi:10.2172/1458356.
Gallego, Nidia C., Contescu, Cristian I., & Burchell, Timothy D. XRD and SANS evaluation of HOPG and Polycrystalline Graphite. United States. doi:10.2172/1458356.
Gallego, Nidia C., Contescu, Cristian I., and Burchell, Timothy D. Fri . "XRD and SANS evaluation of HOPG and Polycrystalline Graphite". United States. doi:10.2172/1458356. https://www.osti.gov/servlets/purl/1458356.
@article{osti_1458356,
title = {XRD and SANS evaluation of HOPG and Polycrystalline Graphite},
author = {Gallego, Nidia C. and Contescu, Cristian I. and Burchell, Timothy D.},
abstractNote = {As the primary construction material used in gas-cooled reactor cores, either of high-temperature (HTR) or very high-temperature (VHTR) design, nuclear graphite must be well characterized and variations in its properties upon high-energy neutron irradiation must be known, understood, and predict ed as accurately as possible before a reactor is built and operational. However, even after more than 70 years of operation of graphite-moderated reactors and intense research on graphite’s behavior in an extreme environment created by high temperatures, irradiation, mechanical stress, and chemically reactive (oxidizing) gaseous environment, questions still remain.},
doi = {10.2172/1458356},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jun 01 00:00:00 EDT 2018},
month = {Fri Jun 01 00:00:00 EDT 2018}
}

Technical Report:

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