You need JavaScript to view this

Review of sorption and diffusion parameters for TVO-92

Technical Report:

Abstract

Teollisuuden Voima Oy (TVO) is investigating the feasibility to dispose of spent nuclear fuel in a final repository constructed in a crystalline rock formation several hundred meters underground. This work is a part of the program of the updated preliminary safety assessment TVO-92. According to the plans the spent fuel, sealed in copper-iron canisters, is emplaced in drillholes below the tunnel floor and surrounded by bentonite clay buffer. The tunnels are backfilled with a mixture of quartz sand (90%) and bentonite (10%). Migration of solutes is retarded by sorption in the backfill and on fracture surfaces of the rocks and by diffusion into fissures and micropores of the rock. In migration calculations retardation due to sorption is derived from distribution ratios of solutes between water and solid. Migration by diffusion in rock is described by diffusion coefficients. Proposals are made for distribution ratios and diffusion coefficients in the backfill and in rocks for the radionuclides of spent significant with respect to safety of the final disposal. The proposals include realistic values besides the conservative values, leading with a high probability to overestimation of radiation doses in the biosphere. (orig.).
Authors:
Hakanen, M; Hoelttae, P [1] 
  1. Helsinki Univ. (Finland). Dept. of Radiochemistry
Publication Date:
Sep 01, 1992
Product Type:
Technical Report
Report Number:
YJT-92-14
Reference Number:
SCA: 052002; PA: AIX-24:007823; SN: 93000932595
Resource Relation:
Other Information: PBD: Sep 1992
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; RADIOACTIVE WASTE DISPOSAL; RADIONUCLIDE MIGRATION; DIFFUSION; SORPTION; BACKFILLING; BENTONITE; FEASIBILITY STUDIES; GROUND WATER; OXIDATION; REDUCTION; ROCKS; SAFETY; SALINITY; SOLUTES; SPENT FUELS; UNDERGROUND DISPOSAL; 052002; WASTE DISPOSAL AND STORAGE
OSTI ID:
10119266
Research Organizations:
Voimayhtioeiden Ydinjaetetoimikunta, Helsinki (Finland)
Country of Origin:
Finland
Language:
English
Other Identifying Numbers:
Other: ON: DE93612762; TRN: FI9200099007823
Availability:
OSTI; NTIS; INIS
Submitting Site:
FIN
Size:
[85] p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Hakanen, M, and Hoelttae, P. Review of sorption and diffusion parameters for TVO-92. Finland: N. p., 1992. Web.
Hakanen, M, & Hoelttae, P. Review of sorption and diffusion parameters for TVO-92. Finland.
Hakanen, M, and Hoelttae, P. 1992. "Review of sorption and diffusion parameters for TVO-92." Finland.
@misc{etde_10119266,
title = {Review of sorption and diffusion parameters for TVO-92}
author = {Hakanen, M, and Hoelttae, P}
abstractNote = {Teollisuuden Voima Oy (TVO) is investigating the feasibility to dispose of spent nuclear fuel in a final repository constructed in a crystalline rock formation several hundred meters underground. This work is a part of the program of the updated preliminary safety assessment TVO-92. According to the plans the spent fuel, sealed in copper-iron canisters, is emplaced in drillholes below the tunnel floor and surrounded by bentonite clay buffer. The tunnels are backfilled with a mixture of quartz sand (90%) and bentonite (10%). Migration of solutes is retarded by sorption in the backfill and on fracture surfaces of the rocks and by diffusion into fissures and micropores of the rock. In migration calculations retardation due to sorption is derived from distribution ratios of solutes between water and solid. Migration by diffusion in rock is described by diffusion coefficients. Proposals are made for distribution ratios and diffusion coefficients in the backfill and in rocks for the radionuclides of spent significant with respect to safety of the final disposal. The proposals include realistic values besides the conservative values, leading with a high probability to overestimation of radiation doses in the biosphere. (orig.).}
place = {Finland}
year = {1992}
month = {Sep}
}