Identification and location of 14C-bearing species in thermally treated neutron irradiated graphites NBG-18 and NBG-25: Pre- and post-thermal treatment-Reference-Cited by-同舟云学术

Identification and location of 14C-bearing species in thermally treated neutron irradiated graphites NBG-18 and NBG-25: Pre- and post-thermal treatment

Published:2015-05 Issue: Volume:460 Page:174-183
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

LaBrier Daniel,Dunzik-Gougar Mary Lou

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference7 articles.

1. Decontamination of nuclear graphite

2. LIMITED OXIDATION OF IRRADIATED GRAPHITE WASTE TO REMOVE SURFACE CARBON-14

3. An oxygen transfer model for high purity graphite oxidation

4. M.L. Dunzik-Gougar, J. Cleaver, D. LaBrier, S. McCrory, T. Smith, Chemical characterization and removal of carbon-14 from irradiated graphite II – 13023, in: WM2013 Conference, Phoenix AZ, February 2013.

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