Hostname: page-component-cd9895bd7-dk4vv Total loading time: 0 Render date: 2024-12-26T18:48:20.876Z Has data issue: false hasContentIssue false

Rate and speciation of volatile carbon-14 and tritium releases from irradiated graphite

Published online by Cambridge University Press:  05 July 2018

G. M. N. Baston*
Affiliation:
AMEC (formerly Serco), B150, Harwell, Didcot, Oxfordshire OX11 0QB, UK
T. A. Marshall
Affiliation:
Research Centre for Radwaste Disposal, School of Earth, Atmospheric and Environmental Science, The University of Manchester, Manchester M13 9PL, UK
R. L. Otlet
Affiliation:
RCD, The Old Stables, East Lockinge, Wantage, Oxfordshire OX12 8QY, UK
A. J. Walker
Affiliation:
RCD, The Old Stables, East Lockinge, Wantage, Oxfordshire OX12 8QY, UK
I. D. Mather
Affiliation:
RCD, The Old Stables, East Lockinge, Wantage, Oxfordshire OX12 8QY, UK
S. J. Williams
Affiliation:
NDA Harwell Office, B587, Curie Avenue, Harwell, Didcot, Oxfordshire OX11 0RH, UK
*
Rights & Permissions [Opens in a new window]

Abstract

Core share and HTML view are not available for this content. However, as you have access to this content, a full PDF is available via the ‘Save PDF’ action button.

The release and migration of gaseous carbon-14 has been identified as a key issue for geological disposal of intermediate-level radioactive wastes in the UK. A significant fraction of carbon-14 in the UK inventory is in irradiated graphite. This paper describes measurements of gaseous carbon-14 releases from irradiated graphite on immersion in alkaline solution. Apparatus has been developed to discriminate organic and inorganic (14CO/14CO2) species in the gas phase by means of selective oxidation and capture. In the initial experiment, small amounts of gaseous carbon-14 (∼4 Bq) were released from 9 g of crushed graphite within a two-week period. In a long-term experiment, cumulative releases were measured periodically from an intact specimen of graphite over a 14 month period. A small fraction of the graphite carbon-14 inventory was released to the gas phase (∼0.004% as CO/CO2 and ∼0.001% associated with organic compounds). A larger quantity of carbon-14, about 0.1%, was released to the solution phase and was thought to be mainly 14CO2, with some possible organic component. In general, the rate of gaseous carbon-14 release decreased with time. The results suggest a small initial release of relatively labile, accessible carbon-14, with longer term release occurring at a much slower rate. Tritium (T) releases were also measured.

Type
Research Article
Creative Commons
Creative Common License - CCCreative Common License - BY
© [2012] The Mineralogical Society of Great Britain and Ireland. This is an open access article distributed under the terms of the Creative Commons Attribution (CC BY) licence (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
Copyright
Copyright © The Mineralogical Society of Great Britain and Ireland 2012

References

Gray, W.J. and Morgan, W.C. (1988) Leaching of 14C and 36C1 from Hanford Reactor Graphite. Pacific Northwest Laboratory Report PNL-6769.Google Scholar
Gray, W.J. and Morgan, W.C. (1989) Leaching of 14C and 36C1 from Irradiated French Graphite. Pacific Northwest Laboratory Report PNL-6989.Google Scholar
Handy, B.J. (2006) Experimental study of C-14 and H-3 Release from irradiated graphite spigot samples in alkaline solution. NNC Report 11996/TR/001.*Google Scholar
Hoch, A.R., Thorne, M.C., Swift, B.T. and Bate, F. (2008) Update of the GPA (03) assessment of the consequences of gas. Serco Report SA/ENV-0948 Issue 2, August 2008.*Google Scholar
Nuclear Decommissioning Authority (2010a) Geological disposal - Near-field Evolution Status Report. RWMD Report NDA/RWMD/033..Google Scholar
Nuclear Decommissioning Authority (2010b) Geological disposal - Gas Status Report. NDA Report NDA/RWMD/037..Google Scholar
Otlet, R.L., Walker, A.J. and Caldwell-Nichols, C.J. (1992) Practical environmental, working area and stack discharge samplers, passive and dynamic, for the measurement of tritium as HTO and HT. Fusion Technology, 21, 550555.CrossRefGoogle Scholar
Takahashi, R., Toyahara, M., Maruki, S. and Ueda, H. (2001) Investigation of morphology and impurity of nuclear grade graphite, and leaching mechanism of carbon-14. In: Nuclear Graphite Waste Management. Proceedings of a Technical Committee meeting held in Manchester, United Kingdom, 1820.October 1999. International Atomic Energy Agency, Vienna.Google Scholar
Walker, A.J. and Otlet, R.L. (1998) Studies on gaseous species of tritium and carbon-14 in environmental air around nuclear establishments. Pp. 159169.in: Environmental Radiochemical Analysis (G.W.A. Newton, editor). Royal Society of Chemistry, London.Google Scholar