Resources

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Analysis of parameters affecting the bending behavior of spent fuel rods
Type:PATRAM Proceedings
Author(s):Konrad Linnemann, Viktor Ballheimer, Jens Sterthaus, Annette Rolle, Frank Wille, Ramil Nasyrow, Dimitrios Papaioannou, Efstathios Vlassopoulos, Vincenzo Rondinella
Abstract:
Transport packages for spent nuclear fuel have to be assessed with respect to specific transport conditions which are defined in the…
Analysis of the Self-Loosening of Packages Impact Limiter Fastening Bolts under Vibrations during Transport
Type:PATRAM Proceedings
Author(s):Xavier KNEMP, Benoit ECKERT, Christian Lalanne, Marie-Thérèse CAILLARD-LIZOT, Christophe Valentin
Abstract:
Bolted impact limiters generally equip extremities of packages used to transport irradiated fuel or high-level waste. These shock absorbers…
Analysis of Transportation Options for Commercial Spent Fuel in the U.S.
Type:PATRAM Proceedings
Author(s):Elena A. Kalinina, Ingrid K. Busch
Abstract:
The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage and associated transportation of spent…
Application of a Decision-Support Tool for Evaluating Radioactive Material Transportation Routing Options and Emergency Preparedness
Type:PATRAM Proceedings
Author(s):Mark Abkowitz, Amanda Bickford
Abstract:
The U.S. Department of Energy, Office of Nuclear Energy is laying the groundwork forimplementing interim storage of spent nuclear fuel (SNF…
Application of High Burnup 9x9 Fuel Model Bundles for Spent Fuel Transport Package Systems
Type:PATRAM Proceedings
Author(s):Yoshiyuki Fujita, Hirotaka Nojima, M. Matsumoto, Takehiro Isono, Tetsuro Takeshita
Abstract:
It is generally assumed in the criticality safety design of spent fuel transport packages that extremely conservative virtual spent fuel,…
Application of practical FSD reduction technique for MCNP code in the spent fuel cask shielding analysis
Type:PATRAM Proceedings
Author(s):Naoto Kubota, Daisuke Shimizu, Tsutomu Matsumoto
Abstract:
In order to apply the MCNP code to shielding analysis of spent fuel casks, the reduction of Fractional Standard Deviation (FSD) is an…
Assessing Radiological Dose to Members of the Public and Workers during Used Nuclear Fuel Transportation
Type:PATRAM Proceedings
Author(s):Ulf Stahmer
Abstract:
Large scale transportation of Canada’s inventory of used nuclear fuel is still several decades away. However, the impact of the used fuel…
Behaviour of Wood Filled Impact Limiters during Fire Test
Type:PATRAM Proceedings
Author(s):Martin Feldkamp, Marko Nehrig, Claus Bletzer, A. Musolff, Frank Wille, Marina Erenberg
Abstract:
Packages for the transport of radioactive material are often equipped with impact limiters consisting of wood, encapsulated by steel sheets…
Bending test device for mechanical integrity studies of spent nuclear fuel rods
Type:PATRAM Proceedings
Author(s):Ramil Nasyrow, Dimitrios Papaioannou, V.V. Rondinella, Efstathios Vlassopoulos, Konrad Linnemann, V. Ballheimer, Jens Sterthaus, Annette Rolle, Frank Wille, S. Caruso
Abstract:
This paper presents data obtained from experiments performed using a bending test set-up developed at the Joint Research Centre (JRC) –…
Bolt Breakage Incident for Low-Level Radioactive Waste Container（1) ― Investigation into Cause and Measures ―
Type:PATRAM Proceedings
Author(s):Shoko Kakiuchi, Koichi Nakama, Hideki Takatsuki, Yutaka Hirose, Misami Hanate
Abstract:
The Nuclear Fuel Transport Co., Ltd. (“NFT”) found that lid anchor bolts (“lid bolts”) onLow-Level Radioactive Waste (“LLW”) containers…
Bolt Breakage Incident for Low-Level Radioactive Waste Container（2）― Quantitative Assessments on Delayed Fracture Sensitivity of Lid Bolts for Low Level Radioactive Waste Container by Slow Strain Rate Test (SSRT)
Type:PATRAM Proceedings
Author(s):Yukio Okabe, Mitsuo Matsumoto, Yutaka Hirose, Jun Takahashi
Abstract:
We found a total of five fractured lid bolts on low-level radioactive waste (ìLLWî) containers in storage from February to June 2015. We…
Brazed and welded cans for transport and storage of damaged fuel rods
Type:PATRAM Proceedings
Author(s):Pierre Lefebvre, Franz Hilbert
Abstract:
For the type B(U)F package NCS 45 leak tight cans are stipulated in the certificate of package approval to provide a barrier for the…
Burst and Tensile Testing of Hydrided Fuel Cladding
Type:PATRAM Proceedings
Author(s):Rick Shimskey, Philip Jensen, Paul MacFarlan, Leigh Lin, Brady Hanson
Abstract:
The U.S. Department of Energy Office of Nuclear Energy, Office of Fuel Cycle Technology has established the Used Fuel Disposition Campaign…
Calculations of safe distance from the point of a severe accident during transportation of a package containing spent nuclear fuels
Type:PATRAM Proceedings
Author(s):Hiroshi Okuno, Fumitaka Watanabe
Abstract:
This paper shows our calculations with a diffusion calculation code, HotSpot, on the effects of a radiological release of fission products…
Cleanliness of transportation cask cavities
Type:PATRAM Proceedings
Author(s):Mathieu Lenoir, Lisa Martin, Emilie Bouyer, Frédéric Lévêque
Abstract:
Within the framework of spent fuel assemblies (SFA) shipments from French NPPs to the AREVA La Hague recycling plant, unexpected foreign…
Clearance and Recycling of an INF-3 Ship
Type:PATRAM Proceedings
Author(s):Jenny Holmström
Abstract:
Swedish Nuclear Fuel and Waste Management Co (SKB) has recently completed the clearance and recycling of MV Sigyn, an INF-3 ship. MV Sigyn…
Collision Risk Assessment Techniques for INF Ship Using AIS Data
Type:PATRAM Proceedings
Author(s):Yoshihiro HIRAO, Daiichiro Ito
Abstract:
We propose techniques of arranging traffic information of a sea area using AIS data and then estimating conditional collision frequency for…
Combustion Simulation of Transportation Package Performance in Severe, Long Duration Fire Using Computational Fluid Dynamics Tools
Type:PATRAM Proceedings
Author(s):Yang Sui
Abstract:
The IAEA regulatory thermal test is designed to bound conditions in historic transportation fire accidents. The regulatory thermal test is…
Communication in the Google Age
Type:PATRAM Proceedings
Author(s):John Simpson
Abstract:
PurposeTo consider the most effective means of communicating safety and security critical information in respect of radioactive material…
Comparison of Neutron Attenuation in Graphene Hybrid Materials
Type:PATRAM Proceedings
Author(s):Danielle Castley, Cameron Goodwin, Ulrike G.K. Wegst
Abstract:
Graphene is a relatively new and exciting carbon allotrope because of its exceptional property profile. While graphene currently attracts…