Scoping calculation of nuclides migration in engineering barrier system for effect of volume expansion due to overpack corrosion and intrusion of the buffer material
Creators
- 1. Waste Isolation Research Division, Waste Management and Fuel Cycle Research Center, Tokai Works, Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)
- 2. Nuclear Energy System Incorporated, Tokyo (Japan)
Description
Corrosion of the carbon steel overpack leads to a volume expansion since the specific gravity of corrosion products is smaller than carbon steel. The buffer material is compressed due to the corrosive swelling, reducing its thickness and porosity. On the other hand, buffer material may be extruded into fractures of the surrounding rock and this may lead to a deterioration of the planned functions of the buffer, including retardation of nuclides migration and colloid filtration. In this study, the sensitivity analyses for the effect of volume expansion and intrusion of the buffer material on nuclide migration in the engineering barrier system are carried out. The sensitivity analyses were performed on the decrease in the thickness of the buffer material in the radial direction caused by the corrosive swelling, and the change in the porosity and dry density of the buffer caused by both compacting due to corrosive swelling and intrusion of buffer material. As results, it was found the maximum release rates of relatively shorter half-life nuclides from the outside of the buffer material decreased for taking into account of a volume expansion due to overpack corrosion. On the other hand, the maximum release rates increased when the intrusion of buffer material was also taking into account. It was, however, the maximum release rates of longer half-life nuclides, such as Cs-137 and Np-237, were insensitive to the change of buffer material thickness, and porosity and dry density of buffer. (author)
Availability note (English)
Available from INIS in electronic formFiles
31062629.pdf
Files
(1.2 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 48 p.
- Report number
- JNC-TN--8400-99-087
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31062629
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- BUFFERS; CARBON STEELS; CORROSION PRODUCTS; DIFFUSION BARRIERS; ENVIRONMENTAL EXPOSURE PATHWAY; EXPANSION; PERFORMANCE TESTING; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE STORAGE; RADIONUCLIDE MIGRATION; ROCKS; SWELLING; VOLUME
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; DEFORMATION; ENVIRONMENTAL TRANSPORT; IRON ALLOYS; IRON BASE ALLOYS; MANAGEMENT; MASS TRANSFER; RADIOACTIVE WASTE MANAGEMENT; STEELS; STORAGE; TESTING; TRANSITION ELEMENT ALLOYS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE STORAGE
Optional Information
- Notes
- 5 refs., 13 figs., 2 tabs.