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1-11 of 11
Keywords: Spent Fuel
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Proceedings Papers
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A051, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92217
... Abstract A full-scale prototype of vertical ventilated spent fuel dry storage canister is tested to evaluate its heat removal performance. Specifically, a temporary shelter is built to resemble the factory encompassing dry storage canisters. Electrical heating components with designed heat...
Proceedings Papers
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A078, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93351
... Abstract This paper describes the loading pattern, safety evaluation and operating experiences of PWR plant off-site Spent Fuel Dry Storage System (SFDSS). According to the limits from the SFDSS criticality and heat-transfer safety analysis, ALARA principle and AFA series fuel characteristics...
Proceedings Papers
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A067, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92870
... spent fuel risk matrix marine transportation risk analysis Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92870 Study on risk of nuclear spent fuel marine transportation Liu Yiqing CGN Uranium Resources Co...
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, V003T11A014, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66590
... Abstract Placing spent fuel into dry cask storage as soon as possible allows decommissioning plants to lower site risk, reduce costs associated with management and maintenance of the spent fuel pool, and accelerate decommissioning. The SENTRY™ Spent Fuel Management System 1 is a dual-purpose...
Proceedings Papers
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T08A003, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15190
... The Korea Atomic Energy Research Institute (KAERI) has been developing pyroprocess for the dry conditioning of PWR spent nuclear fuels since 1997. The ACPF (Advanced spent fuel Conditioning Process Facility) was developed for volume reduction research on spent PWR fuel. Several years later...
Proceedings Papers
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 533-543, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30123
... 08 04 2011 With world stockpiles of used nuclear fuel increasing, the need to address the long-term utilization of this resource is being studied. Many of the transuranic (TRU) actinides in nuclear spent fuel produce decay heat for long durations, resulting in significant nuclear waste...
Proceedings Papers
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 821-825, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48280
... The spent fuel disposal is a very important step during the recycling of nuclear fuel and the operation process is very complex and dangerous. With the fast development of nuclear power reactor in china, more and more spent fuel will occur and should be treated in the near future...
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 351-358, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22456
... around the cladding, but there is little variation across the thickness, of the cladding. It is most significant that all of the hydrides appear to have retained the circumferential orientation typical of prestorage PWR fuel rods. KEYWORDS: Spent Fuel, Dry Storage, Fuel Examination I. INTRODUCTION Some...
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 481-484, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22671
... spent fuel storage decay heat power Accumulation and subsequent storage of actinides from uranium, plutonium, and thorium spent fuel of PWR type reactor is discussed in the paper. During period of accumulation 100 or 300 years, actinides are periodically introduced in the storage...
Proceedings Papers
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 273-281, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49607
... of . DUCTION the end of 2003, EPRI completed a Probabilistic Risk ent of the radiological risks to the public of the life a dry spent fuel storage cask. This study is documented port titled Probabilistic Risk Assessment (PRA) of torage Casks: Quantification and Analysis Report [1]. erformed in order...
Proceedings Papers
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 627-632, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49428
... disposal containment spent fuel high level radioactive waste Proceedings of ICONE12 12th International Conference on Nuclear Engineering April 25-29, 2004, Arlington, Virginia USA 281 Copyright © 2004 by ASME high level radioactive material and waste. Some time after publication, CC N-717...