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Hyun Gook Kang - One of the best experts on this subject based on the ideXlab platform.
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Probabilistic risk assessment on maritime spent nuclear fuel transportation—Part I: Transport CASK damage probability
Reliability Engineering & System Safety, 2017Co-Authors: Robby Christian, Hyun Gook KangAbstract:Abstract This paper proposes a methodology to assess and reduce risks on Spent Nuclear Fuel (SNF) packages from ship collisions with a probabilistic approach. A method to estimate the impact energy upon a collision was elaborated in consideration that whether ships slide or stuck to each other during collision. Structural crash-worthiness of the SNF ship was obtained through a non-linear finite element analysis. CASK damage probability was calculated based on frontal and side CASK impact scenarios. This CASK damage probability was investigated over various transport parameters which include the number of transport CASKs carried per shipment, CASK stowage configuration, CASK loading direction, and ship's cruise velocity. Collision case studies are presented by using reference models of the SNF package, the struck and striking ship. Most and least vulnerable stowage locations on the SNF ship were discovered. The number of CASKs in a shipment and their stowage method which suppressed CASK damage probabilities were identified. The proposed methodology was successful in assisting decision making processes to minimize risks in maritime spent nuclear fuel transportation.
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probabilistic risk assessment on maritime spent nuclear fuel transportation part i transport CASK damage probability
Reliability Engineering & System Safety, 2017Co-Authors: Robby Christian, Hyun Gook KangAbstract:Abstract This paper proposes a methodology to assess and reduce risks on Spent Nuclear Fuel (SNF) packages from ship collisions with a probabilistic approach. A method to estimate the impact energy upon a collision was elaborated in consideration that whether ships slide or stuck to each other during collision. Structural crash-worthiness of the SNF ship was obtained through a non-linear finite element analysis. CASK damage probability was calculated based on frontal and side CASK impact scenarios. This CASK damage probability was investigated over various transport parameters which include the number of transport CASKs carried per shipment, CASK stowage configuration, CASK loading direction, and ship's cruise velocity. Collision case studies are presented by using reference models of the SNF package, the struck and striking ship. Most and least vulnerable stowage locations on the SNF ship were discovered. The number of CASKs in a shipment and their stowage method which suppressed CASK damage probabilities were identified. The proposed methodology was successful in assisting decision making processes to minimize risks in maritime spent nuclear fuel transportation.
Robby Christian - One of the best experts on this subject based on the ideXlab platform.
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Probabilistic risk assessment on maritime spent nuclear fuel transportation—Part I: Transport CASK damage probability
Reliability Engineering & System Safety, 2017Co-Authors: Robby Christian, Hyun Gook KangAbstract:Abstract This paper proposes a methodology to assess and reduce risks on Spent Nuclear Fuel (SNF) packages from ship collisions with a probabilistic approach. A method to estimate the impact energy upon a collision was elaborated in consideration that whether ships slide or stuck to each other during collision. Structural crash-worthiness of the SNF ship was obtained through a non-linear finite element analysis. CASK damage probability was calculated based on frontal and side CASK impact scenarios. This CASK damage probability was investigated over various transport parameters which include the number of transport CASKs carried per shipment, CASK stowage configuration, CASK loading direction, and ship's cruise velocity. Collision case studies are presented by using reference models of the SNF package, the struck and striking ship. Most and least vulnerable stowage locations on the SNF ship were discovered. The number of CASKs in a shipment and their stowage method which suppressed CASK damage probabilities were identified. The proposed methodology was successful in assisting decision making processes to minimize risks in maritime spent nuclear fuel transportation.
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probabilistic risk assessment on maritime spent nuclear fuel transportation part i transport CASK damage probability
Reliability Engineering & System Safety, 2017Co-Authors: Robby Christian, Hyun Gook KangAbstract:Abstract This paper proposes a methodology to assess and reduce risks on Spent Nuclear Fuel (SNF) packages from ship collisions with a probabilistic approach. A method to estimate the impact energy upon a collision was elaborated in consideration that whether ships slide or stuck to each other during collision. Structural crash-worthiness of the SNF ship was obtained through a non-linear finite element analysis. CASK damage probability was calculated based on frontal and side CASK impact scenarios. This CASK damage probability was investigated over various transport parameters which include the number of transport CASKs carried per shipment, CASK stowage configuration, CASK loading direction, and ship's cruise velocity. Collision case studies are presented by using reference models of the SNF package, the struck and striking ship. Most and least vulnerable stowage locations on the SNF ship were discovered. The number of CASKs in a shipment and their stowage method which suppressed CASK damage probabilities were identified. The proposed methodology was successful in assisting decision making processes to minimize risks in maritime spent nuclear fuel transportation.
Mohammad Amin Kiani - One of the best experts on this subject based on the ideXlab platform.
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Effectiveness of the neutron-shield nanocomposites for a dual-purpose CASK of Bushehr's Water–Water Energetic Reactor (VVER) 1000 nuclear-power-plant spent fuels
Nuclear Engineering and Technology, 2017Co-Authors: Rezaeian, Jamshid Kamali, Seyed Javad Ahmadi, Mohammad Amin KianiAbstract:Abstract In order to perform dry interim storage and transportation of the spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose CASKs can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose CASK was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose CASK utilizing the recently developed materials of epoxy/clay/B 4 C and epoxy/clay/B 4 C/carbon fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the CASK. By utilization of epoxy/clay/B 4 C instead of an ethylene glycol/water mixture, the dose rates on the side surface of the CASK due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.
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effectiveness of the neutron shield nanocomposites for a dual purpose CASK of bushehr s water water energetic reactor vver 1000 nuclear power plant spent fuels
Nuclear Engineering and Technology, 2017Co-Authors: Mahdi Rezaeian, Jamshid Kamali, Seyed Javad Ahmadi, Mohammad Amin KianiAbstract:Abstract In order to perform dry interim storage and transportation of the spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose CASKs can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose CASK was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose CASK utilizing the recently developed materials of epoxy/clay/B 4 C and epoxy/clay/B 4 C/carbon fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the CASK. By utilization of epoxy/clay/B 4 C instead of an ethylene glycol/water mixture, the dose rates on the side surface of the CASK due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.
Bernhard Droste - One of the best experts on this subject based on the ideXlab platform.
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Consideration of aging mechanism influence on transport safety of dual purpose CASKs for spent nuclear fuel or HLW
Packaging Transport Storage and Security of Radioactive Material, 2014Co-Authors: Bernhard Droste, Steffen Komann, Frank Wille, Annette Rolle, Ulrich Probst, Sven SchubertAbstract:AbstractWhen storage of spent nuclear fuel or high level waste is carried out in dual purpose CASKs (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable and can be justified and certified permanently throughout that period. The effects of aging mechanisms (e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. Consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all CASK components that cannot be directly inspected or changed without opening the CASK cavity, like the inner parts of the closure system and the CASK internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging is not the subj...
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Considerations of aging mechanisms influence on transport safety and reliability of dual purpose CASKs for spent nuclear fuel or HLW
2014Co-Authors: Bernhard Droste, Steffen Komann, Frank Wille, Annette Rolle, Ulrich Probst, Sven SchubertAbstract:When storage of spent nuclear fuel (SNF) or high-level waste (HLW) is done in dual purpose CASKs (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable, and can be justified and certified permanently throughout that period. The effects of aging mechanisms (like e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. The consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all CASK components which cannot be directly inspected or changed without opening the CASK cavity, what are the inner parts of the closure system and the CASK internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging is not subject of technical aspects only, but also of "intellectual" aspects, like changing standards, scientific/ technical knowledge development and personal as well as institutional alterations. Those aspects are to be considered in the management system of the license holders and in appropriate design approval update processes. The paper addresses issues which are subject of an actual IAEA TECDOC draft "Preparation of a safety case for a dual purpose CASK containing spent nuclear fuel".
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internal CASK content collisions during drop test of transport CASKs for radioactive materials
Packaging Transport Storage and Security of Radioactive Material, 2013Co-Authors: Thomas Quercetti, Viktor Ballheimer, Bernhard Droste, Karsten MüllerAbstract:In transport CASKs for radioactive materials, significantly large axial and radial gaps between CASK and internal content are often present because of certain specific geometrical dimensions of the content (e.g. spent fuel elements) or thermal reasons. The possibility of inner relative movement between content and CASK will increase if the content is not fixed. During drop testing, these movements can lead to internal CASK content collisions, causing significantly high loads on the CASK components and the content itself. Especially in vertical drop test orientations onto a lid side of the CASK, an internal collision induced by a delayed impact of the content onto the inner side of the lid can cause high stress peaks in the lid and the lid bolts with the risk of component failure as well as impairment of the leak tightness of the closure system. This paper reflects causes and effects of the phenomenon of internal impact on the basis of experimental results obtained from instrumented drop tests with transpo...
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internal CASK content collisions during drop test of transport CASKs for radioactive materials
Packaging Transport Storage and Security of Radioactive Material, 2013Co-Authors: Thomas Quercetti, Viktor Ballheimer, Bernhard Droste, Karsten MüllerAbstract:In transport CASKs for radioactive materials, significantly large axial and radial gaps between CASK and internal content are often present because of certain specific geometrical dimensions of the content (e.g. spent fuel elements) or thermal reasons. The possibility of inner relative movement between content and CASK will increase if the content is not fixed. During drop testing, these movements can lead to internal CASK content collisions, causing significantly high loads on the CASK components and the content itself. Especially in vertical drop test orientations onto a lid side of the CASK, an internal collision induced by a delayed impact of the content onto the inner side of the lid can cause high stress peaks in the lid and the lid bolts with the risk of component failure as well as impairment of the leak tightness of the closure system. This paper reflects causes and effects of the phenomenon of internal impact on the basis of experimental results obtained from instrumented drop tests with transpo...
Sven Schubert - One of the best experts on this subject based on the ideXlab platform.
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Consideration of aging mechanism influence on transport safety of dual purpose CASKs for spent nuclear fuel or HLW
Packaging Transport Storage and Security of Radioactive Material, 2014Co-Authors: Bernhard Droste, Steffen Komann, Frank Wille, Annette Rolle, Ulrich Probst, Sven SchubertAbstract:AbstractWhen storage of spent nuclear fuel or high level waste is carried out in dual purpose CASKs (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable and can be justified and certified permanently throughout that period. The effects of aging mechanisms (e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. Consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all CASK components that cannot be directly inspected or changed without opening the CASK cavity, like the inner parts of the closure system and the CASK internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging is not the subj...
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Considerations of aging mechanisms influence on transport safety and reliability of dual purpose CASKs for spent nuclear fuel or HLW
2014Co-Authors: Bernhard Droste, Steffen Komann, Frank Wille, Annette Rolle, Ulrich Probst, Sven SchubertAbstract:When storage of spent nuclear fuel (SNF) or high-level waste (HLW) is done in dual purpose CASKs (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable, and can be justified and certified permanently throughout that period. The effects of aging mechanisms (like e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. The consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all CASK components which cannot be directly inspected or changed without opening the CASK cavity, what are the inner parts of the closure system and the CASK internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging is not subject of technical aspects only, but also of "intellectual" aspects, like changing standards, scientific/ technical knowledge development and personal as well as institutional alterations. Those aspects are to be considered in the management system of the license holders and in appropriate design approval update processes. The paper addresses issues which are subject of an actual IAEA TECDOC draft "Preparation of a safety case for a dual purpose CASK containing spent nuclear fuel".