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Proceedings Papers

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92147
... Abstract With the continuous advance of the mass construction of nuclear power in China, it has become an irresistible trend to use mature commercial-off-the-shelf (COTS) to perform safety functions in the safety important instrumentation and control (I&C) systems to reduce the construction...
Proceedings Papers

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A016, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90907
... Abstract As an integrated nuclear engineer and operator, EDF has a strong background in studying extreme natural hazards for its Nuclear Power Plants (NPPs) fleet safety demonstration. The state-of-the art evolution and the development of natural hazards Probabilistic Safety Analysis provide...
Proceedings Papers

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90522
... public acceptance. nuclear public safety regulation Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-90522 AFFECTING FACTORS AND ASPECTS OF DEVELOPING NUCLEAR PUBLIC ACCEPTANCE STRATEGIES Haomiao Lin China...
Proceedings Papers

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A048, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93216
... more and more close to people’s life, and nuclear and radiation safety has also attracted more and more attention from all walks of life. Therefore, while making effective use of nuclear technology, it is very necessary to do a good job of risk identification and safety management and control. Doing...
Proceedings Papers

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91667
... Abstract Risk informed safety margin characteristics (RISMC) analysis Method, is a safety analysis method which combines probability safety analysis and determinism safety analysis of nuclear power plant. General RISMC analysis platform “CARS” (Coupling Platform for Advanced Risk Simulation...
Proceedings Papers

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A057, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93395
... because it could assess overall impacts of risks and help to identify vulnerabilities to determine next steps to address security risks. With the integration of information system and physical system, cyber security of information system and functional safety of physical system interact with each other...
Proceedings Papers

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A056, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91722
... Abstract Radiation exposure is an essential measure of social welfare. Every day the public was exposed to radiation, whether they were aware of it or not. Public people can only receive no more than 1mSv of radiation in a year based on Basic Safety Radiation Protection Regulations 2010 under...
Proceedings Papers

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66385
... Abstract The Generation IV (GEN-IV) international forum is a framework for international co-operation in research and development for the next generation of nuclear energy systems. Within the GEN-IV sodium-cooled fast reactor (SFR) system arrangement, the SFR Safety and Operation (SO) project...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64335
... Abstract In high-level waste treatment plants, rooms where the highly radioactive sources (such as the vitrification containers) are operated have high radiation protection risk. On the purpose of ensuring the safety of operators, it is necessary to design corresponding shielding walls, windows...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A002, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16185
..., European safety authorities released new reference levels in the framework of WENRA 2013 (Western European Nuclear Regulators Association) standards for new reactors [1] to address external hazards more severe than the design basis hazards. Considering this input, the French and UK nuclear regulators have...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A016, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16664
... novel methodology and results can have an impact on future consideration about Long-Term Operation (LTO) of NPPs. ageing station blackout MELCOR FEM safety LTO Study of the ageing effects on the lower head failure in a PWR reactor R. Lo Frano, S. Paci University of Pisa Pisa, Italy P...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A021, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16186
... Abstract According to the Periodic Safety Review Process, the safety level is re-assessed every ten years, considering national and international operational feedback, evolution of knowledge and best available practices. Protection against natural hazards is part of this safety level re...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A012, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16136
... Abstract Over the years, power plants have been hit by numerous severe weather events (storm, flood, heat wave...). EDF (Electricity of France) and ASN (Nuclear Safety Authority) want to assess the future impact of severe weather events on the power plants. Furthermore, recent research...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A022, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16187
... Abstract Following the Fukushima Daiichi accident, the Western European Nuclear Regulators Association (WENRA) updated in 2014 the safety reference levels (SRL) for existing reactors, introducing a new chapter specific to natural hazards. In 2015, in preparation for the 4th periodic safety...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A054, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16755
... fraction (ARF) of a 7A drum’s contents when exposed to a pool fire than what is assumed in current safety basis documents. This potentially different ARF is currently unknown because, while studies have been performed in the past to quantify ARF for 7A drums in a fire, no comprehensive measurements have...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A012, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16662
... reactor overpressurization). It is safety relevant (key) system of the fusion reactor because by condensing the steam generated during such accident event allows to damp the overpressure. This paper deals with experimental and theoretical analyses of the DCC at sub-atmospheric pressure. The similitude...
Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 457-462, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29326
... distributed within the lower spring-plenum region of the LWR fuel. If successful this innovation can be implemented in existing and next generation LWRs and may: • reduce accident source term (releasable FPGs); • enhance reactor safety and acceptance; • extend fuel life suppressing clad swelling and fuel...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 123-129, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22137
... accidents, quench, reflood, LWR, safety. TION of an uncovered, overheated Light Water Reactor e by water is the main accident management terminating a severe accident transient. But, before cceeds in cooling the fuel elements, the injected nder certain circumstances, trigger an enhanced the Zircaloy...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 815-823, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22423
... and restored th HTRs, bringing which can make these reactors more acceptable for the public: the modular concept, not exceeding 200 to 600 MWth (depending on the savings. Moreover the safety of a modular HTR, based on inherent physical properties of the system, which cannot break down or be bypassed by human...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 591-597, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22213
... ypes that will be ion IV systems. The inherent safety, proliferation wer reactors are s in nuclear power ter Reactors mperature alled Fast Breeder Reactors (LMFBR), Molten-Salt Reactors (MSR) and, perhaps, some other recently suggested innovative systems. The HTGR concept can be considered as one...