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RD&D-Programme 2004 - SKB

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A system for documentation of the long-lived waste has been developed by <strong>SKB</strong>. The system<br />

resembles the one for SFR waste, but also takes into account the fact that documentation takes<br />

place progressively. This is due to the fact that the waste is in some cases stored as raw waste<br />

for a long time before being given its final form for disposal.<br />

Conclusions in RD&D 2001 and its review<br />

SKI concludes that it is reasonable to focus the work on the radionuclides that contribute most<br />

to the calculated dose, such as chlorine-36 and molybdenum-93, but that <strong>SKB</strong> should also be<br />

prepared to study other nuclides that may be important at the next safety assessment.<br />

Newfound knowledge since RD&D 2001<br />

The long-lived LILW will be kept track of by <strong>SKB</strong> in a similar way as the waste destined for<br />

SFR. With time, this will give us a better picture of the radionuclide inventory in the waste.<br />

Studies have been conducted on behalf of <strong>SKB</strong> at the Division of Nuclear Physics at Lund<br />

University to reduce the detection limit for nickel-59 in steel material. An earlier measurement<br />

method was mainly developed with regard to specimen preparation. The detection limit has<br />

been reduced by a factor of 20 compared with the previous level. In recent years, measurements<br />

have been performed on both steel material from BWR reactors and reactor water from PWR<br />

reactors.<br />

A project has been started at the same division at Lund University to measure carbon-14 in ion<br />

exchange resins from Swedish reactors. Previously, carbon-14 has been measured in graphite<br />

from the decommissioned research reactor at KTH in Stockholm. Literature reviews have been<br />

conducted for the purpose of identifying suitable measurement methods for carbon-14 measurements<br />

in ion exchange resins.<br />

<strong>SKB</strong> has also had measurements performed of the chlorine content of steel material at Imperial<br />

College in London. The purpose of these measurements was to permit more accurate calculation<br />

of the content of chlorine-36 in steel material from the Swedish reactors. The detection limits<br />

in these measurement series varied between 0.14 and 1.5 mg/kg (ppm). The majority of the<br />

specimens that were analyzed lay below the detection limits. The project entailed that an earlier<br />

method for cleaning of specimens had to be modified to prevent the chloride content from being<br />

affected in cases where the specimens contained quantities of molybdenum and tungsten.<br />

<strong>Programme</strong><br />

See section 25.5.<br />

25.3.1 Final repository for other long-lived waste<br />

A layout for the final repository for other long-lived waste was prepared in 1996. This repository<br />

was to be able to receive long-lived LILW /25-1/.<br />

Conclusions in RD&D 2001 and its review<br />

The authorities /25-2/ note the lack of a coherent account of design studies and design requirements<br />

as well as requirements that must be made on a candidate site in order for it to meet the<br />

requirements made on the design of the final repository for other long-lived waste.<br />

Newfound knowledge since RD&D 2001<br />

<strong>SKB</strong> has not conducted any new studies of this nature.<br />

330 RD&D-<strong>Programme</strong> <strong>2004</strong>

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