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Organisationseinheit der BAM
Hydrogen is present in anhydrous materials as a result of their synthesis and of their environment during conservation. IBA provides techniques to measure H concentration depth profiles allowing to identify various aspects of the materials including the history of objects such as gemstones used in cultural heritage.
A newly established ERDA set-up, using an external microbeam of alpha particles, has been developed to study hydrated near-surface layers in quartz and sapphire by non-destructive H depth profiling in different atmospheres. The samples were also analysed using resonant NRA and SIMS.
Anoxische Objektbehandlungen gegen Schädlingsbefall stellen eine besonders materialverträgliche und umweltschonende Alternative zu chemischen Bekämpfungsverfahren dar. Die Wirksamkeit hängt jedoch von der Dauer, dem Restsauerstoffgehalt sowie der Temperatur und Feuchtigkeit ab. Unterschiedliche Arten von Schadinsekten sind verschieden tolerant gegenüber sauerstoffarmen Bedingungen. Insbesondere bei Behandlungsbedingungen von unter 24° C und mehr als 0,5 % Restsauerstoffgehalt stößt das Verfahren an die Grenze der Zuverlässigkeit. In Versuchsreihen unter standardisierten Bedingungen erwiesen sich insgesamt 12 von 34 im Projekt untersuchte Insektenarten hierbei als widerstandsfähig. Davon als besonders tolerante Arten sind Hylotrupes bajulus, Lasioderma serricorne, Trogoderma parabile und Mezium affine zu nennen.
Mit dem entwickelten UWB-Sensoriksystem können durch elektromagnetische Wellen Bewegungen von Schädlingen innerhalb geschlossener Holzobjekte berührungslos erfasst werden. Voraussetzung für die eindeutige Detektion der Schädlingsaktivität ist neben der digitalen Signalverarbeitung zur Filterung und Extraktion des Nutzsignals, die genügend hohe Eindringtiefe, die ausreichend ist, wenn Schädlingsvorkommen häufig dicht unter der Holzoberfläche gelegen sind. Die Versuchsergebnisse haben gezeigt, dass bereits eine einzelne Trockenholztermite der Art Incisitermes marginipennis hinter einer 5 cm dicken Holzplatte aufgespürt werden kann. Somit erscheint das Messsystem potentiell für die Erfolgskontrolle einer Anoxia-Behandlung an Museumsgütern geeignet.
The decommissioning or refurbishment of nuclear facilities necessitates either the storage or disposal of large radioactive components such as steam generators, pressurizers, reactor pressure vessels and heads, and coolant pumps, to list the major contributors. These components or objects are large in size and mass, measuring up to approximately 6 meters in diameter, up to 20 meters in length, and weighing over 400 000 kg. In many situations, the components are transported off-site to a storage, disposal or recycling/treatment facility. Previously, many large objects had to be transported under special arrangement.
The decommissioning or refurbishment of nuclear facilities necessitates either the storage or disposal of large radioactive components such as steam generators, pressurizers, reactor pressure vessels and heads, and coolant pumps, to list the major contributors. These components or objects are large in size and mass, measuring up to approximately 6 meters in diameter, up to 20 meters in length, and weighing over 400 000 kg. In many situations, the components are transported off-site to a storage, disposal or recycling/treatment facility. Previously, many large objects had to be transported under special arrangement.
The latest 2018 edition of the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material, No. SSR-6 [1], incorporates regulations for the shipment of large objects as a new category of surface contaminated object, SCO-III, based on the IAEA “performance package” concept. This paper provides background and practical guidance on these regulations.
Additionally, the experiences of BAM with the appoval of two steam converters of the NPP Lingen are presented as the first approval process for SCO-III objects in Germany.
The primary additions to SSR-6 include SCO-III classification and requirements, approval and administrative requirements for the new classification, and the addition of SCO-III to the proper shipping
name for UN 2913. Advisory material drafted for the new requirements will be included in the next revision of SSG-26, Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material, expected to be published soon.
Note that at this time the proposed provisions for large objects do not include components such as reactor vessels, due to the more limited experience and greater radioactivity levels. The SCO-III concept lays the groundwork and may be extended to cover other large objects that are classified as low specific activity (LSA) material in the future.
Spent nuclear fuel which is generated in the operation of nuclear reactors needs to be safely managed following its removal from the reactor core. On-site power reactor storage pools were designed on the assumption that after a short period of time spent nuclear fuel would be removed for reprocessing and disposal or further storage elsewhere. The amount of highly radioactive spent fuel that needs to be stored over longer periods of time is growing and additional storage capacity is required. One of the widely used options for additional storage capacity is the use of casks for dry storage of spent fuel. Among various existing dry storage concepts, several Member States are utilizing a concept of dual purpose casks (DPCs). This publication provides practical advice on the structure and contents of a DPC integrated safety case with reference to existing IAEA requirements relevant to the licensing and use of transport and storage casks for spent fuel.
Since 2005, several European countries, coordinated by the European Association of Competent Authorities (EACA), have been developing a guide on contents and structure of the documentation demonstrating the compliance with the regulations for packages for the transport of radioactive material (package design safety report, PDSR). This guide has been periodically improved, considering feedback from Designers and authorities.
Taking into account the successful application of this guide in Europe, in 2013 the International Atomic Energy Agency (IAEA) decided to establish a similar guide as an IAEA document for promotion of worldwide use. The development of this IAEA guide started from the latest version of the European PDSR guide. In 2016/2017, during a 120-day review period, comments on the draft were received from member states and international organizations. These were incorporated into the draft in a series of meetings in 2017.
In another meeting in December 2018 the draft was updated to be in line with the latest revision of the IAEA Regulations for the Safe Transport of Radioactive Material (SSR-6).
In this process the draft has been improved significantly, regarding structure as well as implementation of a graded approach depending on the package type, and clarified.
This paper points to the major considerations in developing the guide and important improvements over the last version of the European PDSR guide.