Mechanical and Thermal Safety Analyses and Demonstra Tions For Cubic DCI Multipurpose Containers

Völzke, Holger; Wieser, G.; Zencker, Uwe; Droste, Bernhard

doi:10.1179/rmt.1997.8.3-4.247

Cited by 3 publications

(1 citation statement)

References 1 publication

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“…Actually, former fire test at BAM with ion exchange resin showed that this is not valid in every case. 4 In this experiment, a cubical container (261?76 1?6 m) with a wall thickness of 150 mm and filled with wet ion exchange resin was exposed to a fire test. The content was equipped with several thermocouples.…”

Section: Specific Conditions Of Containers With Thick Wallsmentioning

confidence: 99%

Safety assessment aspects of type B(U) packages containing wet intermediate level waste

Nehrig

Bletzer

Wille

2012

Packaging, Transport, Storage & Security of Radioactive Mat

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In Germany, the mechanical and thermal safety assessment of approved packages for the transport of RAM is carried out by BAM as the competent authority according to the International Atomic Energy Agency regulations. BAM was involved in several approval procedures with ductile cast iron containers containing wet intermediate level waste. These contents, which are not dried, only drained, consist of saturated ion exchange resin and a small amount of free water. Compared to the safety assessment of packages with dry content, attention must be paid to some more specific points. The physical and chemical compatibility of the content itself and of the content with materials of the package must be shown. From the mechanical resistance point of view, the package has to withstand the forces resulting from the freezing liquid. The most interesting point, however, is the pressure build-up inside the package due to vapourisation. This could be caused by radiolysis of the liquid and must be taken into account for the storage period. The paper deals primarily with the pressure build-up inside the package caused by the regulatory thermal test (30 min at 800uC) as part of the cumulative test scenario under accident conditions of transport. To determine the pressure, the temperature distribution in the content must be calculated for the whole period from the beginning of the thermal test until cooling down. In this case, calculating the temperature distribution requires, besides the consideration of conduction and heat radiation, consideration of evaporation and condensation including the associated processes of transport.

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Section: Specific Conditions Of Containers With Thick Wallsmentioning

confidence: 99%

Safety assessment aspects of type B(U) packages containing wet intermediate level waste

Nehrig

Bletzer

Wille

2012

Packaging, Transport, Storage & Security of Radioactive Mat

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show abstract

Pressure Build-Up Inside Packages Containing Wet Intermediate Level Radioactive Waste due to Thermal Loads

Nehrig

Bletzer

Wille

2012

Volume 7: Operations, Applications and Components

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Over the last years several transport approval procedures were finished for ductile cast iron containers containing wet intermediate level waste. BAM was involved in the assessment of mechanical and thermal aspects, activity release and material and component behavior regarding fulfillment of the regulatory requirements. The radioactive contents of these package designs which were not dried, only drained, consist of saturated ion exchange resin and a small amount of free water. Regarding wet contents, the most interesting point, however, is the pressure build-up inside the package due to vaporization. This could be caused by radiolysis of the liquid and must be taken into account for the storage period. The paper deals primarily with the pressure build-up inside the package caused by the regulatory thermal test (30 min at 800°C) as part of the cumulative test scenario under accident conditions of transport. The pressure build-up is estimated by calculation in a very conservative way regarding conduction and heat radiation. To get trustworthy results without an exact specification of the content, physical fire tests should be conducted. This paper will result in the strong advice, that contents should be dried to ensure a positive outcome of the safety assessment.

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Experiences and Status in Safety Assessment Methods within the Scope of Licensing Procedures for Multi-Purpose Flasks in Germany

Völzke¹,

Droste²,

Rödel³

2000

International Journal of Radioactive Materials Transport

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Mechanical and Thermal Safety Analyses and Demonstra Tions For Cubic DCI Multipurpose Containers

Cited by 3 publications

References 1 publication

Safety assessment aspects of type B(U) packages containing wet intermediate level waste

Safety assessment aspects of type B(U) packages containing wet intermediate level waste

Pressure Build-Up Inside Packages Containing Wet Intermediate Level Radioactive Waste due to Thermal Loads

Experiences and Status in Safety Assessment Methods within the Scope of Licensing Procedures for Multi-Purpose Flasks in Germany

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