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Keywords: safety
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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
Paper No: ICONE28-66385
... Generation-IV SFR safety operation Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-66385 ACTIVITIES OF THE GIF SAFETY AND OPERATION PROJECT OF SODIUM-COOLED FAST REACTOR SYSTEMS Hidemasa Yamano1 Marie-Sophie...
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
Paper No: ICONE28-64335
...Abstract 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...
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
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
Paper No: ICONE2020-16664
.... Keywords: Ageing; Station Blackout; MELCOR, FEM, Safety; LTO 1. INTRODUCTION The most important aim of an NPP safety is to prevent reactor fuel overheating. This is obtained by designing and operating the nuclear plant in order to guarantee the core adequate coolability. During an accident, the 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, V002T08A021, August 4–5, 2020
Paper No: ICONE2020-16186
...IMPACT OF CLIMATE CHANGE ON EDF'S NUCLEAR FACILITIES: CLIMATE WATCH APPROACH L. Guinard1, S. Parey2, H. Cordier1, L. Grammosenis1 1Electricité de France (EDF), Lyon, France 2Electricité de France, R&D, Saclay, France ABSTRACT According to the Periodic Safety Review Process, the safety level is 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
Paper No: ICONE2020-16136
...Abstract 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
Paper No: ICONE2020-16187
... 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 review of its 900 MW units, EDF aimed...
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
Paper No: ICONE2020-16755
... release 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...
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
Paper No: ICONE2020-16662
... fusion 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...
Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 457-462, May 17–21, 2010
Paper No: ICONE18-29326
... reactor safety and acceptance extend fuel life suppressing clad swelling and fuel failure reduce thermal neutron poisons in high flux core regions improve operational and economical performance require only minor changes to fuel pin assembly and use use in LWRs with no license or tech...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 123-129, April 14–18, 2002
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
Paper No: ICONE10-22423
... by the last 2 decade 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...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 1043-1049, April 14–18, 2002
Paper No: ICONE10-22644
... is substantially negative. Fuel burnup is about three times the current natural-uranium burnup. AECL NG CANDU Reactor Physics Slightly Enriched Fuel D 2 O Moderator H 2 O Coolant Safety Control Proceedings of ICONE 10 10TH International Conference on Nuclear Engineering Arlington, VA, USA...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 591-597, April 14–18, 2002
Paper No: ICONE10-22213
... full inherent safety, competitive economics and proliferation resistance. The work discussed here is centered on a modularized small-size High Temperature Gas-cooled Reactor (HTGR) concept. This paper discusses the possibility of maintaining long-term operation on one fuel loading through utilization...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 21-28, April 25–29, 2004
Paper No: ICONE12-49030
... points. ALARA Contamination Diver Dose Dosimetry Exposure Fuel Radiation Reactor REM Robotic Safety Shielding Suppression Pool Underwater e chamber. Because water provides excellent shielding, divers are able to work in areas where radiological exposures would be prohib perfor...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 273-281, April 25–29, 2004
Paper No: ICONE12-49607
... is even lower; with, again, no early fatalities and a cancer risk of 4.2E−12. Probabilistic Risk Assessment PRA Spent Fuel Cask Safety Proceedings of ICONE12 12th International Conference on Nuclear Engineering life cycle, where the life cycle is divided into three phases: loading, standard...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 457-462, April 25–29, 2004
Paper No: ICONE12-49371
... into service in the next fifty years, together with their associated fuel cycles. INPRO has been implemented in two phases. In the framework of its Phase 1A, the task group Safety of Innovative Nuclear Systems examined the needs to be met by innovative nuclear systems and defined, in a hierarchical order...
Proceedings Papers

Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 1-7, July 17–20, 2006
Paper No: ICONE14-89017
... 17 09 2008 Criticality safety evaluations implement requirements to proof of sufficient sub critical margins outside of the reactor environment for example in fuel fabrication plants. Basic criticality data (i.e., criticality standards) are used in the determination of sub critical...
Proceedings Papers

Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 451-456, July 17–20, 2006
Paper No: ICONE14-89286
... that. Several SSCs have shorter life times than NPP’s life time. Ageing is one of the factors that decrease the SSC life time. Due to ageing, if are not replaced, some SSCs, or groups of redundant SSCs, become critical looking to safety. Some questions for what to do in the situation when a SSC must be replaced...