Corrosion of Lead and Lead Alloys in Simulated Repository Environments

1987 ◽  
Vol 112 ◽  
Author(s):  
Frank E. Goodwin ◽  
Richard J. Guenther
Keyword(s):  
Nuclear Waste ◽  
Corrosion Products ◽  
Research Organization ◽  
Corrosion Tests ◽  
Corrosion Rates ◽  
Lead Alloys ◽  
Lead Zinc ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Waste Repositories

AbstractA series of corrosion tests were sponsored by the International Lead Zinc Research Organization, Inc. and conducted by Battelle Northwest to obtain information regarding the suitability of lead for applications in the containment of high-level nuclear waste. Two grades of unalloyed lead and two lead alloys were exposed to basalt, salt, and tuff simulated repository environments for times up to 1 year and temperatures from 55 to 200°C. Information was obtained on the corrosion rates, corrosion products, and concentration of lead in the test liquids under these conditions, which were intended to simulate the anticipated environments in candidate U.S. nuclear waste repositories. Leachates from the 12-month tests were analyzed in order to prepare synthetic leachates that were used to conduct scoping evaluations of the transport of lead in basalt and tuff environments.

Mcc Corrosion Tests at Reference Testing Conditions for A27 Cast steel in Hanford Ground Water

1986 ◽  
Vol 84 ◽  
Author(s):  
M.D. Merz ◽  
F. Gerber ◽  
R. Wang
Keyword(s):  
Pacific Northwest ◽  
Pressure Vessel ◽  
Static Pressure ◽  
Cast Steel ◽  
Statistical Treatment ◽  
Testing Conditions ◽  
Corrosion Tests ◽  
Corrosion Rates ◽  
High Level Nuclear Waste ◽  
High Level

AbstractThe Materials Characterization Center (MCC) at Pacific Northwest Lab- oratory is performing three kinds of corrosion tests for the Basalt Waste Isolation Project (BWIP) to establish the interlaboratory reproducibility and uncertainty of corrosion rates of container materials for high-level nuclear waste. The three types of corrosion tests were selected to address two distinct conditions that are expected in a repository constructed in basalt. An air/steam test is designed to address corrosion during the operational period and static pressure vessel and flowby tests are designed to address corrosion under conditions that bound the condi ring the post-closure period of the repository.The results of tests at reference testing conditions, which were defined to facilitate interlaboratory comparison of data, are presented. Data are reported for the BWIP/MCC-105.5 Air/Steam Test, BWIP/MCC-105.1 Static Pressure Vessel, and BWIP/MC-105.4 Flowby Test. In those cases where data are available from a second laboratory, a statistical analysis of interlaboratory results is reported and expected confidence intervals for mean corrosion rates are given. Other statistical treatment of data include analyses of the effects of vessel-to-vessel variations, test capsule variations for the flowby test, and oven-to-oven variations for air/steam tests.

scholarly journals Towards higher temperatures in nuclear waste repositories

2020 ◽  
Vol 205 ◽  
pp. 01001
Author(s):  
Antonio Gens ◽  
Ramon B. de Vasconcelos ◽  
Sebastià Olivella
Keyword(s):  
Nuclear Waste ◽  
Large Scale ◽  
Maximum Temperature ◽  
Spent Fuel ◽  
Thermally Induced ◽  
Large Scale Field ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Host Rocks ◽  
Waste Repositories

Recently, there is a tendency to explore the possibility of increasing the maximum design temperature in deep geological repositories for high-level nuclear waste and spent fuel. In the paper, a number of issues related to the use of higher temperatures are reviewed. Both bentonite barriers and argillaceous host rocks are addressed. An application involving the modelling of a large-scale field test conducted at a maximum temperature of 140ºC is presented. It is shown that currently available theoretical formulations and computer codes are capable to deal with temperatures above 100ºC and to reproduce satisfactorily the thermally-induced overpressures in the rock.

scholarly journals UO2 as New Filling Material for Cesium Retention in High-Level Nuclear Waste Repositories

2015 ◽  
Vol 32 (10) ◽  
pp. 854-857
Author(s):  
Albert Martínez-Torrents ◽  
Javier Giménez ◽  
Joan de Pablo ◽  
Ignasi Casas
Keyword(s):  
Nuclear Waste ◽  
Filling Material ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Waste Repositories
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