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Featured researches published by Marko Nehrig.


ASME 2014 Pressure Vessels and Piping Conference | 2014

NUMERICAL APPROACH FOR CONTAINMENT ASSESSMENT OF TRANSPORT PACKAGES UNDER REGULATORY THERMAL TEST CONDITIONS

Jens Sterthaus; Viktor Ballheimer; Claus Bletzer; Konrad Linnemann; Marko Nehrig; Frank Wille

The requirements of the IAEA safety standards for Type B(U) packages include the thermal test as part of test sequences that represents accident conditions of transport. In comparison to mechanical tests, e.g., 9 m drop onto an unyielding target with short impact durations in a range of approximately 10 ms to 30 ms, the extended period of 30 min is defined in regulations for exposure of a package to a fire environment. Obviously, the required containment capability of the package has to be ensured not only after completing the test sequence but also over the course of the fire test scenario.Especially, deformations in the sealing area induced by the non-uniform thermal dilation of the package can affect the capability of the containment system. Consequently, thermo-mechanical analyses are required for the assessment.In this paper some aspects of finite element analysis (FEA) of transport packages with bolted closure systems under thermal loading are discussed. A generic FE model of a cask is applied to investigate the stress histories in the bolts, lid, and cask body as well as the deformations in the sealing area and the compression conditions of the gasket. Based on the parameter variations carried out, some recommendations in regard to modeling technique and results interpretation for such kind of analyses are finally given.Copyright


Archive | 2018

Basic of Transport and Storage of Radioactive Materials

Holger Völzke; Thomas Quercetti; Viktor Ballheimer; Marko Nehrig; Dietmar Wolff; Frank Wille

Transport and storage of radioactive materials are performed in countries with policy of either closed or open nuclear fuel cycle. The related technologies have been established by accumulation of experiences and researches including demonstrative tests using full scale or scale models and analyses. Those are essential before commercialization, but are often costly and time consuming. Such demonstrative works should not be repeated meaninglessly, but can be shared through this kind of book and used by readers and the future generations to advance the technology effectively. This book systematically provides findings from lots of valuable researches on safety of transport and storage of radioactive materials under normal and accident conditions that have an impact on basis of safe regulations, designs, and operations.


ASME 2017 Pressure Vessels and Piping Conference | 2017

Behavior of Wood Filled Impact Limiters During the IAEA Thermal Test

Martin Feldkamp; Marina Erenberg; Marko Nehrig; Claus Bletzer; André Musolff; Thorsten Schönfelder; Frank Wille

Packages for the transport of radioactive material are often equipped with impact limiters consisting of wood, encapsulated by steel sheets. These impact limiters shall ensure that transport casks meet the IAEA safety requirements. After damage caused by the mechanical tests the package has to withstand a severe fire scenario. It is required that the mechanical tests have to produce maximum damage, taking into account the thermal test. Furthermore, any damage, which would give rise to increased radiation or loss of containment or affect the confinement system after the thermal test, should be considered. Concerning the thermal test, the IAEA safety requirements state that during and following the fire test, the specimen shall not be artificially cooled and any combustion of materials of the package shall be permitted to proceed naturally. Different works from the French Institute for Radiological Protection and Nuclear Safety (IRSN) and BAM show that additional energy supply from a pre-damaged impact limiter to the cask could occur caused by smoldering of the wood. This effect should be considered within the safety assessment of the package. A heat wave from the fire could overlap with the additional energy from the impact limiter in the sealing system. In 2015 BAM conducted small scale fire tests with wood filled metal drums showing continuing combustion processes during the cooling down phase. As not much is known about smoldering processes in wood filled impact limiters, it is highly complex to define pre-damage of impact limiters, which are conservative, regarding the most damaging energy flow from the impact limiter to the containment system in dependence of time. More research has to be done to develop models to examine the effects of smoldering impact limiters on the containment of packages for the assessment. The process of smoldering is described with regard to the requirements in the thermal safety assessment. Parameters influencing the smoldering process are identified. BAM operates test facilities to examine the issue of mechanical damage, combustion and heat transfer of packages for transport of radioactive material. A thermal test will take place with a wood filled test specimen with a diameter of about 2.3 meters. The aim is to understand the phenomena of smoldering under the consideration of relevant regulatory boundary conditions.


ASME 2016 Pressure Vessels and Piping Conference | 2016

Effects of Additional Gases Resulting From Residual Water Inside ILW Packages

Marko Nehrig; Frank Wille; Annette Rolle; Konrad Linnemann

Packages for intermediate level waste (ILW) often contain residual water besides the actual waste. The water either exists as obvious free water or it may be bound physically or chemically, e.g. as pore water. A water driven gas generation could occur by vaporisation and by radiolysis. Steam as the result of vaporisation causes an increasing pressure inside a package and can affect corrosion. Vaporisation and condensation processes itself change the thermal behavior of the content especially during strongly unsteady thermal situations like accident fire situations. Radiolysis changes the chemical composition of the content which could cause an unexpected interaction, e.g. hydrogen embrittlement. Besides the pressure build-up the radiolysis of water generates hydrogen and oxygen, which can be highly flammable respectively explosive. The gas generation caused by vaporisation and radiolysis must be taken into account during the design and the safety assessment of a package. Pressure build-up, a changed thermal behavior and content chemistry, and especially the risk of accumulation of combustible gases exceeding the limiting concentration for flammability has to be considered in the safety assessment. Approaches to ensure the transportability of stored packages due to radiolysis will be discussed.


Safe and Secure Transport and Storage of Radioactive Materials | 2015

Thermal performance of transportation packages for radioactive materials

Frank Wille; Marko Nehrig; Martin Feldkamp

Prevention of damage caused by heat is one of the objectives during package safety evaluation. This chapter describes basics of heat transfer and major aspects of regulatory requirements. Package temperature criteria and fire test conditions are explained. Special package design features regarding material properties and safety evaluation concepts are discussed. Experimental fire testing is performed by pool fire or with the help of a furnace. Analysis by numerical or analytical approaches show temperature gradients and whether compliance with the regulatory requirements and specified design temperatures is met. The tightness of the package lid system influenced by geometry changes is in the focus of a holistic thermo-mechanical approach considering the entire mechanical and thermal load conditions according the regulatory requirements.


ASME 2012 Pressure Vessels and Piping Conference | 2012

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

Marko Nehrig; Claus Bletzer; Frank Wille

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.Copyright


Archive | 2018

Internal Pressure build-up of Waste Packages with Wet Contents Under Fire Impact

Marko Nehrig; Frank Wille


Archive | 2017

Aspects of Assessment of Packages with Wood Filled Impact Limiters during Fire Tests

Martin Feldkamp; Marina Erenberg; Marko Nehrig; Claus Bletzer; André Musolff; Frank Wille; Thorsten Schönfelder


Archive | 2015

Combustion of wood encapsulated in steel sheets during fire test

Martin Feldkamp; Marko Nehrig; Claus Bletzer; André Musolff; Frank Wille


Archive | 2013

Pressure Build-Up During the Fire Test in Type B(U) Packages Containing Water - 13280

Martin Feldkamp; Marko Nehrig; Claus Bletzer; Frank Wille

Collaboration


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Frank Wille

Bundesanstalt für Materialforschung und -prüfung

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Claus Bletzer

Bundesanstalt für Materialforschung und -prüfung

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Martin Feldkamp

Bundesanstalt für Materialforschung und -prüfung

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André Musolff

Bundesanstalt für Materialforschung und -prüfung

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Konrad Linnemann

Bundesanstalt für Materialforschung und -prüfung

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Marina Erenberg

Bundesanstalt für Materialforschung und -prüfung

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Thorsten Schönfelder

Bundesanstalt für Materialforschung und -prüfung

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Viktor Ballheimer

Bundesanstalt für Materialforschung und -prüfung

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Annette Rolle

Bundesanstalt für Materialforschung und -prüfung

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Dietmar Wolff

Bundesanstalt für Materialforschung und -prüfung

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