The Experts below are selected from a list of 84 Experts worldwide ranked by ideXlab platform
Kusbaryanto - One of the best experts on this subject based on the ideXlab platform.
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The effectiveness of education of methicillin-resistant Staphylococcus aureus (MRSA) infection prevention and control (IPC) with directive discourse to improve handwashing compliance.
Enfermería Clínica, 2020Co-Authors: KusbaryantoAbstract:Abstract Objective The incidence rate of microbial exposure remains high among nurses. Paramedics play a vital role in transmitting the nosocomial infection in the hospital. This research aims to analyze the education effectivity of MRSA IPC with directive discourse to improve handwashing compliance among nurses. Methods This is quasi-experimental research using a pretest–posttest non-control design and has obtained an ethical Approval Certificate issued by the hospital ethical committee. A research subject is a group of 25 nurses. Results The data test uses the Wilcoxon test to determine the measuring result of handwashing compliance before and after the treatment. The value of p = 0.018 (p Conclusions The education of MRSA IPC with directive discourse is effective to improve the handwashing compliance among nurses in the hospitals.
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The effectiveness of education of methicillin-resistant Staphylococcus aureus (MRSA) infection prevention and control (IPC) with directive discourse to improve handwashing compliance.
Enfermeria clinica, 2020Co-Authors: KusbaryantoAbstract:The incidence rate of microbial exposure remains high among nurses. Paramedics play a vital role in transmitting the nosocomial infection in the hospital. This research aims to analyze the education effectivity of MRSA IPC with directive discourse to improve handwashing compliance among nurses. This is quasi-experimental research using a pretest-posttest non-control design and has obtained an ethical Approval Certificate issued by the hospital ethical committee. A research subject is a group of 25 nurses. The data test uses the Wilcoxon test to determine the measuring result of handwashing compliance before and after the treatment. The value of p=0.018 (p<0.05) means there is a difference before and after the treatment. As handwashing awareness increases, so does the compliance. The education of MRSA IPC with directive discourse is effective to improve the handwashing compliance among nurses in the hospitals. Copyright © 2020 Elsevier España, S.L.U. All rights reserved.
Frank Wille - One of the best experts on this subject based on the ideXlab platform.
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authority experience during design Approval procedure for packages loaded with special encapsulations for damaged spent nuclear fuel
2019Co-Authors: K Linnemann, Steffen Komann, Thorsten Schonfelder, Lars Müller, Frank WilleAbstract:The first German package design Approval Certificate for a dual purpose cask intended for loading with damaged spent nuclear fuel was issued recently. BAM as part of the competent authority system in Germany carried out a comprehensive assessment procedure with respect to the mechanical and thermal design, the release of radioactive material and the quality assurance aspects of manufacturing and operation. Packages for the transport and storage of radioactive material have been assessed by BAM for many years, thus the common assessment procedure is well-known and good practice. Up to now only SNF without defects or HLW with well-defined properties were designated for long-term Interim storage and transports afterwards. Due to Germany’s nuclear phase out all other kinds of spent nuclear fuel in particular damaged spent nuclear fuel shall be packed as well. Damaged spent nuclear fuel needs a tight closure with Special encapsulations and clearly defined properties in Germany. In addition, these encapsulations shall be long-term durable, because they are not accessible after loading in a packaging within periodical inspections. The main difference to Standard package components is that encapsulations with a permanent closure achieve their specified conditions not after manufacturing but only during operation, after loading and closing. To ensure compliance with the specific conditions, special measures for quality assurance are necessary during operation of each encapsulation, e.g. drying and sealing, which were assessed by BAM. The present paper gives an overview of the conducted assessment from BAM and point out the findings concerning to the special closure lid of the approved encapsulation, which is screwed and welded. A wide verification concept is necessary to show the specific tightness under transport conditions. Together with quality assurance measures during first operation steps these encapsulations with damaged spent nuclear fuel can be handled like standard fuel assemblies in approved package designs.
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Requirements for management systems for manufacturing of transport packages: the new revision of BAM-GGR 011 guideline
2019Co-Authors: Martin Neumann, O. Schilling, Christian Kuschke, A. Darnstädt, Sven Schubert, U. Günther, Frank WilleAbstract:In accordance with IAEA SSR-6 para 306 a management system shall be established and implemented to ensure compliance with the relevant provisions of the IAEA regulations. BAM has issued an update of the guideline: the BAM-GGR 011. The new revision describes necessary quality assurance measures for design, manufacture, testing, documentation, use, maintenance and inspection of packagings for package designs requiring competent authority Approval for the transport of radioactive material. The measures can be categorised as system-related and design-related. They are independently approved and monitored by the German competent authority BAM and its authorised expert (BAM/T). The qualification of the organisation applying for the design Approval Certificate is reviewed in the context of the design Approval procedure. The quality assurance measures for manufacture consist of three main steps. Pre-assessment of manufacturing documents such as quality plans, specifications etc., Manufacturing inspections according the pre-assessed documents and inspection before commissioning including documentation review. Periodic inspections during operation as well as relevant specifications for use and maintenance ensure that the properties specified in the Approval Certificate are preserved over the package life time. Special provisions for the return on experience regarding operational feedback for design, manufacture, use, maintenance and inspection are given. Special focus shall be given here to the rearranged and meanwhile established system of manufacturing inspections. This includes more transparent roles for a) the Producers authorised inspection 11282 representative, b) the independent inspection expert (S), acting on behalf of the manufacturer with acceptance of BAM, and c) BAM or its authorised expert (BAM/T). Additional attention shall be drawn to the management of deviations during manufacturing and provisions for maintenance and periodic inspections.
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Assessment experience on packages loaded with damaged spent nuclear fuel for transport after storage
2018Co-Authors: Lars Müller, Steffen Komann, Thorsten Schonfelder, Viktor Ballheimer, Frank WilleAbstract:In 2017 the first German package Approval Certificate was issued for a dual purpose cask (DPC) design with encapsulated damaged spent nuclear fuel. At the Bundesanstalt fur Materialforschung und -prufung (BAM) a comprehensive assessment procedure was carried out with respect to the mechanical and thermal design, the containment design and quality assurance for manufacturing and operation. Main objective of this procedure was to verify the Package Design Safety Report (PDSR) fulfils the requirements according to the IAEA regulations SSR-6. Until now only standard spent nuclear fuel assemblies were designated for interim storage and transports. Due to nuclear phase out in Germany all other kinds of SNF in particular damaged fuel has to be packed. Therefore specific requirements have to be considered in accordance with international experiences written in IAEA technical reports. In Germany damaged spent nuclear fuel (DSNF) needs a tight encapsulation with special encapsulations and clearly defined properties. Due to the limited amount of DSNF these encapsulations are designed for storage and transport in existing packages. From the assessment experience it has been seen, corresponding PDSR need an extensively expansion to cover the design of these encapsulations and their influences on the package. Then such well-defined encapsulations can be handled like standard fuel assemblies. The main difference to standard package components is, encapsulations with permanent closure achieve their specified condition not after manufacturing but only during operation after loading and closing. Thus specific handling instruction and test procedures are necessary especially for welding, where BAM is able to survey the quality of this first part of operation.
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MECHANICAL/THERMAL PACKAGE DESIGN SAFETY ASSESSMENT AND MANUFACTURING QUALITY ASSURANCE OF SPENT FUEL TRANSPORT CASK NCS 45
2010Co-Authors: Christian Kuschke, Frank Wille, Tino Neumeyer, Bernhard DrosteAbstract:The NCS 45 package is designed for a variety of radioactive contents ranging from irradiated PWR, BWR and FBR fuel rods, parts of fuel rods as well as non-fissile radioactive material. BAM assessed the applicants safety analysis concept and the appropriate report with respect of requirements according to transport regulations under routine, normal and accident transport conditions related to mechanical design and thermal design, activity release and quality assurance aspects. The assesment concept of the safety report was a combination of drop test program, analytic and numerical calculations as well as various components tests. The paper will give details of BAM activities in the official safety assessment that had been summarized in the BAM design examination Certificate which was a prerequisite for the Package Design Approval Certificate issued by the German competent authority.
Henri Romazzotti - One of the best experts on this subject based on the ideXlab platform.
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Exceptional Fatigue Performances for Umbilical’s Super Duplex Seam Welded Tube Solutions
Volume 1A: Offshore Technology, 2014Co-Authors: Olivier Wagner, Jérôme Peultier, Jean-philippe Roques, Gilles Thevenet, Henri RomazzottiAbstract:Since the last five years, an innovative technology for umbilical’s seam welded super duplex stainless steel tubes (grade 2507, UNS S32750) has been developed in order to meet new technical challenges. An extensive program of qualification, based on 4 dimensions covering the full manufacturing range, i.e. internal diameter and wall thickness, has been set. More than 11000 test results demonstrated the efficiency and the stability of the manufacturing process. The results were also confirming the expected properties of the tubes, in term of mechanical characteristics, corrosion resistance and manufacturing tolerances. At the end of this qualification phase, a Type Approval Certificate was delivered by an independent and official certifying authority demonstrating then, the suitability of the product for offshore static applications.The next step was to confirm the fatigue performance of the product to meet the requirements of umbilicals for dynamic applications.This paper describes how a dedicated fatigue test protocol has been jointly defined between a Major O&G player and the tube supplier. This protocol has been built in order to test the 3 dimensions already produced during the first step of the qualification, considering tube samples with and without orbital weld. Fatigue test programs are known to be very sensitive to the test parameters, i.e. temperature, test frequency and dimensional properties of the samples. As a consequence, special attention is paid to the description of the testing methodology, the selection of the acceptance criteria and the definition of the testing parameters. Finally, the results of this program are presented and discussed in order to assess the capability of the product with respect to the defined acceptance criteria.© 2014 ASME
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Design Advantages on Umbilical Systems Brought by a New High Performance SDSS Tube
Volume 1: Offshore Technology, 2013Co-Authors: Olivier Wagner, Guy Durand, Jérôme Peultier, Anne Courbot, Jean-philippe Roques, Henri RomazzottiAbstract:Subsea umbilical systems developed for deep offshore applications become more and more demanding regarding injection capacity, number of functionalities and water depth. Some applications, such as subsea boosting, subsea separation or gas lift are even more severe, leading to tube temperature, which can exceed, in some cases 70°C.These operating conditions and requirements are significantly impacting the performance of the main umbilical. The most common solution, to avoid such issues, is to design thicker tubes to improve the strength of the umbilical cross section. The positive effect of the wall thickness increase has to be opposed to major drawbacks, such as weight increase and fatigue performance degradation generating more issues than providing solutions.To face these challenges, Vallourec Umbilicals, with the technical support of TOTAL SA headquarter Technology Division, has developed a new manufacturing process for seam welded stainless steel tubes (SAF 2507), with higher mechanical properties and tighter wall thickness tolerances. The benefit of this innovation is to provide for a given application (i. e. pressure, water depth and temperature) thinner tubes able to meet severe operating conditions without impacting performances of the umbilical structure.This paper, after a description of the manufacturing process and product qualification protocol (that led to a Type Approval Certificate from Bureau Veritas in October 2012), presents the technical advantages brought by seam welded solution, compared to seamless super duplex tubes.Copyright © 2013 by ASME
Lars Müller - One of the best experts on this subject based on the ideXlab platform.
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authority experience during design Approval procedure for packages loaded with special encapsulations for damaged spent nuclear fuel
2019Co-Authors: K Linnemann, Steffen Komann, Thorsten Schonfelder, Lars Müller, Frank WilleAbstract:The first German package design Approval Certificate for a dual purpose cask intended for loading with damaged spent nuclear fuel was issued recently. BAM as part of the competent authority system in Germany carried out a comprehensive assessment procedure with respect to the mechanical and thermal design, the release of radioactive material and the quality assurance aspects of manufacturing and operation. Packages for the transport and storage of radioactive material have been assessed by BAM for many years, thus the common assessment procedure is well-known and good practice. Up to now only SNF without defects or HLW with well-defined properties were designated for long-term Interim storage and transports afterwards. Due to Germany’s nuclear phase out all other kinds of spent nuclear fuel in particular damaged spent nuclear fuel shall be packed as well. Damaged spent nuclear fuel needs a tight closure with Special encapsulations and clearly defined properties in Germany. In addition, these encapsulations shall be long-term durable, because they are not accessible after loading in a packaging within periodical inspections. The main difference to Standard package components is that encapsulations with a permanent closure achieve their specified conditions not after manufacturing but only during operation, after loading and closing. To ensure compliance with the specific conditions, special measures for quality assurance are necessary during operation of each encapsulation, e.g. drying and sealing, which were assessed by BAM. The present paper gives an overview of the conducted assessment from BAM and point out the findings concerning to the special closure lid of the approved encapsulation, which is screwed and welded. A wide verification concept is necessary to show the specific tightness under transport conditions. Together with quality assurance measures during first operation steps these encapsulations with damaged spent nuclear fuel can be handled like standard fuel assemblies in approved package designs.
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Assessment experience on packages loaded with damaged spent nuclear fuel for transport after storage
2018Co-Authors: Lars Müller, Steffen Komann, Thorsten Schonfelder, Viktor Ballheimer, Frank WilleAbstract:In 2017 the first German package Approval Certificate was issued for a dual purpose cask (DPC) design with encapsulated damaged spent nuclear fuel. At the Bundesanstalt fur Materialforschung und -prufung (BAM) a comprehensive assessment procedure was carried out with respect to the mechanical and thermal design, the containment design and quality assurance for manufacturing and operation. Main objective of this procedure was to verify the Package Design Safety Report (PDSR) fulfils the requirements according to the IAEA regulations SSR-6. Until now only standard spent nuclear fuel assemblies were designated for interim storage and transports. Due to nuclear phase out in Germany all other kinds of SNF in particular damaged fuel has to be packed. Therefore specific requirements have to be considered in accordance with international experiences written in IAEA technical reports. In Germany damaged spent nuclear fuel (DSNF) needs a tight encapsulation with special encapsulations and clearly defined properties. Due to the limited amount of DSNF these encapsulations are designed for storage and transport in existing packages. From the assessment experience it has been seen, corresponding PDSR need an extensively expansion to cover the design of these encapsulations and their influences on the package. Then such well-defined encapsulations can be handled like standard fuel assemblies. The main difference to standard package components is, encapsulations with permanent closure achieve their specified condition not after manufacturing but only during operation after loading and closing. Thus specific handling instruction and test procedures are necessary especially for welding, where BAM is able to survey the quality of this first part of operation.
Steffen Komann - One of the best experts on this subject based on the ideXlab platform.
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authority experience during design Approval procedure for packages loaded with special encapsulations for damaged spent nuclear fuel
2019Co-Authors: K Linnemann, Steffen Komann, Thorsten Schonfelder, Lars Müller, Frank WilleAbstract:The first German package design Approval Certificate for a dual purpose cask intended for loading with damaged spent nuclear fuel was issued recently. BAM as part of the competent authority system in Germany carried out a comprehensive assessment procedure with respect to the mechanical and thermal design, the release of radioactive material and the quality assurance aspects of manufacturing and operation. Packages for the transport and storage of radioactive material have been assessed by BAM for many years, thus the common assessment procedure is well-known and good practice. Up to now only SNF without defects or HLW with well-defined properties were designated for long-term Interim storage and transports afterwards. Due to Germany’s nuclear phase out all other kinds of spent nuclear fuel in particular damaged spent nuclear fuel shall be packed as well. Damaged spent nuclear fuel needs a tight closure with Special encapsulations and clearly defined properties in Germany. In addition, these encapsulations shall be long-term durable, because they are not accessible after loading in a packaging within periodical inspections. The main difference to Standard package components is that encapsulations with a permanent closure achieve their specified conditions not after manufacturing but only during operation, after loading and closing. To ensure compliance with the specific conditions, special measures for quality assurance are necessary during operation of each encapsulation, e.g. drying and sealing, which were assessed by BAM. The present paper gives an overview of the conducted assessment from BAM and point out the findings concerning to the special closure lid of the approved encapsulation, which is screwed and welded. A wide verification concept is necessary to show the specific tightness under transport conditions. Together with quality assurance measures during first operation steps these encapsulations with damaged spent nuclear fuel can be handled like standard fuel assemblies in approved package designs.
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Assessment experience on packages loaded with damaged spent nuclear fuel for transport after storage
2018Co-Authors: Lars Müller, Steffen Komann, Thorsten Schonfelder, Viktor Ballheimer, Frank WilleAbstract:In 2017 the first German package Approval Certificate was issued for a dual purpose cask (DPC) design with encapsulated damaged spent nuclear fuel. At the Bundesanstalt fur Materialforschung und -prufung (BAM) a comprehensive assessment procedure was carried out with respect to the mechanical and thermal design, the containment design and quality assurance for manufacturing and operation. Main objective of this procedure was to verify the Package Design Safety Report (PDSR) fulfils the requirements according to the IAEA regulations SSR-6. Until now only standard spent nuclear fuel assemblies were designated for interim storage and transports. Due to nuclear phase out in Germany all other kinds of SNF in particular damaged fuel has to be packed. Therefore specific requirements have to be considered in accordance with international experiences written in IAEA technical reports. In Germany damaged spent nuclear fuel (DSNF) needs a tight encapsulation with special encapsulations and clearly defined properties. Due to the limited amount of DSNF these encapsulations are designed for storage and transport in existing packages. From the assessment experience it has been seen, corresponding PDSR need an extensively expansion to cover the design of these encapsulations and their influences on the package. Then such well-defined encapsulations can be handled like standard fuel assemblies. The main difference to standard package components is, encapsulations with permanent closure achieve their specified condition not after manufacturing but only during operation after loading and closing. Thus specific handling instruction and test procedures are necessary especially for welding, where BAM is able to survey the quality of this first part of operation.