Cement Solidification of Residual Metal Oxide from Radioactive Waste
Creators
- 1. Korea Atomic Energy Research Institute, 989-111 Daedeokdaero, Yuseong, Daejeon 305-353 (Korea, Republic of)
Description
A lot of uranium contaminated soil and concrete waste is generated from the dismantlement of uranium conversion facilities. There are several disposal methods for radioactive materials such as regulation exemption, decontamination and long-term storage. It is necessary for us to achieve the permanent disposal of radioactive waste. The methods for solidifying radioactive waste include cement solidification, asphalt solidification, and polymer solidification. Cement solidification has several advantages such as well-known materials and technologies, various applications, and reasonable cost. On the contrary, it has certain disadvantages such as a large volume expansion of solidification for radioactive waste. Because cement solidification has excellent structural strength and a shielding effect, it is widely used for the permanent disposal of radioactive waste. Cement solidification operates as a barrier against the leaching of nuclides during radioactive waste disposal. To evaluate the criteria of KORAD (Korea Radioactive Waste Agency), integrity tests on the solidification of radioactive waste need to be performed. In this study, to inspect the criteria of KORAD, we carried out the cement solidification of residual metal oxide from radioactive waste. An integrity inspection such as the pressure strength, inundation, and leaching test on cement solidification was performed. We also analyzed the experimental results according to the criteria of KORAD. The calculation of the leachability index on the primary and secondary cement solidification for leaching detection of nuclides is carried out. The integrity of primary and secondary cement solidification is evaluated. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 114
- Journal Issue
- 1
- Journal Page Range
- p. 269-272
- ISSN
- 0003-018X
Conference
- Title
- Annual Meeting of the American Nuclear Society
- Dates
- 12-16 Jun 2016
- Place
- New Orleans, LA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52032129
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CEMENTS; ISOTOPES; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTES; SHIELDING; SOLIDIFICATION; URANIUM
- Descriptors DEC
- ACTINIDES; BUILDING MATERIALS; ELEMENTS; MANAGEMENT; MATERIALS; METALS; PHASE TRANSFORMATIONS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES
Optional Information
- Notes
- 14 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States