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Diffusion of uranium in compacted sodium bentonite

Technical Report:

Abstract

In the study the diffusion of uranium dissolved from uranium oxide fuel was studied experimentally in compacted sodium bentonite (Wyoming bentonite MX-80). The experiments were carried out by the through-diffusion method. The parameters varied in the study were the density of bentonite, salt content of the solution and redox conditions. Uranium was dissolved under aerobic conditions in order to simulate oxic conditions possibly caused by radiolysis in the repository.
Authors:
Muurinen, A; Lehikoinen, J [1] 
  1. Technical Research Centre of Finland, Espoo (Finland). Reactor Lab.
Publication Date:
Sep 01, 1992
Product Type:
Technical Report
Report Number:
YJT-92-13
Reference Number:
SCA: 052002; PA: AIX-24:007822; SN: 93000932594
Resource Relation:
Other Information: PBD: Sep 1992
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; BENTONITE; DIFFUSION; URANIUM; AEROBIC CONDITIONS; EXPERIMENTAL DATA; GROUND WATER; RADIOACTIVE WASTE DISPOSAL; REDOX REACTIONS; SALINITY; SPENT FUELS; UNDERGROUND DISPOSAL; URANIUM OXIDES; 052002; WASTE DISPOSAL AND STORAGE
OSTI ID:
10119261
Research Organizations:
Voimayhtioeiden Ydinjaetetoimikunta, Helsinki (Finland)
Country of Origin:
Finland
Language:
English
Other Identifying Numbers:
Other: ON: DE93612761; TRN: FI9200098007822
Availability:
OSTI; NTIS; INIS
Submitting Site:
FIN
Size:
[40] p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Muurinen, A, and Lehikoinen, J. Diffusion of uranium in compacted sodium bentonite. Finland: N. p., 1992. Web.
Muurinen, A, & Lehikoinen, J. Diffusion of uranium in compacted sodium bentonite. Finland.
Muurinen, A, and Lehikoinen, J. 1992. "Diffusion of uranium in compacted sodium bentonite." Finland.
@misc{etde_10119261,
title = {Diffusion of uranium in compacted sodium bentonite}
author = {Muurinen, A, and Lehikoinen, J}
abstractNote = {In the study the diffusion of uranium dissolved from uranium oxide fuel was studied experimentally in compacted sodium bentonite (Wyoming bentonite MX-80). The experiments were carried out by the through-diffusion method. The parameters varied in the study were the density of bentonite, salt content of the solution and redox conditions. Uranium was dissolved under aerobic conditions in order to simulate oxic conditions possibly caused by radiolysis in the repository.}
place = {Finland}
year = {1992}
month = {Sep}
}