0

Full Content is available to subscribers

Subscribe/Learn More  >

The Radioactivity Analysis of 14C in the Graphite Samples From the Dismantled KRR-1&2 Sites by a High Temperature Furnace and a LSC

[+] Author Affiliations
Hee Reyoung Kim, Wanno Lee, Kun Ho Chung, Mun Ja Kang, Dong Gyu Lee, Geun Sik Choi, Chang Woo Lee

Korea Atomic Energy Research Institute, Daejeon, South Korea

Paper No. ICEM2007-7145, pp. 557-561; 5 pages
doi:10.1115/ICEM2007-7145
From:
  • The 11th International Conference on Environmental Remediation and Radioactive Waste Management
  • 11th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B
  • Bruges, Belgium, September 2–6, 2007
  • Conference Sponsors: Nuclear Division and Environmental Engineering Division
  • ISBN: 978-0-7918-4339-0 | eISBN: 0-7918-3818-8
  • Copyright © 2007 by ASME

abstract

The radioactivity of 14 C of the graphite samples from the dismantled Korea Research Reactor 1&2 (the KRR-1&2) site was analyzed and proposed to be disposed of as a low level radioactive waste rather than self-disposed of. The graphite wastes, with a weight of seven tons, have been generated during the dismantling of a research reactor with a capacity of one MW from 1995 to 2006. The graphite was used as a moderator for the research reactor and so has been radioactivated by thermal neutron. It was thought that the graphite wastes mainly included a radioisotope of stable carbon, 14 C, a pure beta emitter with a half life of 5,730 years and with a maximum decay energy of 156 keV. Therefore, it has been requested to see whether the dismantled graphite radioactive wastes including 14 C can be self-disposed of or not. In the present study, the radioactivity of 14 C in the graphite sample used in the research reactor was analyzed by using a commercialized high temperature furnace and a Liquid Scintillation Counter (LSC). The combustion temperature of the furnace was five hundred degrees centigrade and especially the temperature in the catalyst region was eight hundred degrees centigrade. The recovery from the furnace was 95% for 14 C and the LSC had a quenching efficiency of approximately 66%. Carbosorb was used as a trapping solution for 14 C. The radioactivity of 14 C was measured by a LSC through the procedure of a pre-treatment such as the combustion of a sample in the temperature range of 500–800 degrees centigrade by a high temperature furnace, trapping of 14 C into carbosorb and cocktailing it with a scintillator. The radioactivity was analyzed to have a concentration with a value of much more than a domestic legal limit for a self-disposal. And an individual effective dose rate estimation was also carried out. Finally, it is suggested that the graphite wastes from the dismantled research reactor should be disposed of at a low level radioactive waste disposal site and monitored.

Copyright © 2007 by ASME

Figures

Tables

Interactive Graphics

Video

Country-Specific Mortality and Growth Failure in Infancy and Yound Children and Association With Material Stature

Use interactive graphics and maps to view and sort country-specific infant and early dhildhood mortality and growth failure data and their association with maternal

NOTE:
Citing articles are presented as examples only. In non-demo SCM6 implementation, integration with CrossRef’s "Cited By" API will populate this tab (http://www.crossref.org/citedby.html).

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In