Dec 22 2015
Canada Carbon is pleased to provide the following update on the status of the ASTM research program which will lead to the development of standard assessment protocols to determine the chemical purity and neutron absorption potential for natural graphites intended for nuclear applications.
As reported September 30, 2015, Canada Carbon's thermally upgraded Miller graphite was selected for assessment towards developing a standard natural graphite material for nuclear applications. Four international laboratories, one from the US and three from the EU with membership in Subcommittee D02.F0 on Manufactured Carbon and Graphite Products of ASTM International have participated in the round-robin testing of the Miller graphite, contributing eight analytical datasets arising from three different Glow Discharge Mass Spectrometry ("GDMS") instrumental platforms. These experimental results are currently being interpreted in accordance with ASTM Standard E691-2011: "Standard Practice for Conducting an Interlaboratory Study to Determine the Precision of a Test Method". The GDMS analytical results will be compared with those arising from two different preparatory methods for Inductively Coupled Plasma Mass Spectrometry ("ICP-MS") analysis, as well as those arising from Particle Induced X-Ray Emission ("PIXE"), each of which is capable of producing analytical results of similar analytical sensitivity. All analytical assessments were conducted at no cost to Canada Carbon.
Canada Carbon Executive Chairman and Chief Executive Officer Mr. R. Bruce Duncan stated, "We were honoured to be asked in late September 2015 to provide ASTM with samples of the thermally upgraded Miller graphite (99.9998% purity) for the development of a new nuclear standard for natural graphite. Additionally, representatives of Canada Carbon, while attending the December 2015 ASTM conference in Austin, Texas, were invited to join the ASTM Subcommittee DO2.F0, Manufactured Carbon and Graphite Products. We are pleased to accept the invitations."