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Conception of transport cask with advanced safety, aimed at transportation and storage of spent nuclear fuel of power reactors, which meets the requirements of IAEA in terms of safety and increased stability during beyond-design-basis accidents and acts o
Type:PATRAM Proceedings
Author(s):R.I. Il’kaev, V.Z. Matveev, A.I. Morenko, V.I. Shapovalov, A.G. Semenov, V.M. Sergeyev, V.K. Orlov, V.V. Shatalov, V.A. Seredenko, V.T. Gotovchikov, M. Jonathan Haire, C. W. Forsberg
Abstract:
The report is devoted to the problem of creation of a new generation of multi-purpose universal transport cask with advanced safety, aimed…
CONSTOR? V/TC Drop Tests. Pre-Test Analysis by Finite Element Method
Type:PATRAM Proceedings
Author(s):Walter Völzer, Sabine König, Karl Klein, Chi-Fung Tso, Sarah Owen, Christopher Monk
Abstract:
The CONSTOR? family of steel-concrete-steel sandwich cask designs have been developed to fulfil both the internationally valid IAEA…
CONSTOR® full-scale prototype drop test and measuring program
Type:PATRAM Proceedings
Author(s):Sabine König, Rudolf Diersch, Thomas Quercetti
Abstract:
The CONSTOR® steel-sandwich cask was developed as a cost-effective design by using conventional mechanical engineering technologies and…
Containment Performance of Transportable Storage Casks at 9m Drop Test
Type:PATRAM Proceedings
Author(s):Hitoshi TOBITA, Kenji Araki
Abstract:
Spent fuel transportable storage casks usually have a double lid closure system, which consists of primary and secondary lids, and gaskets…
Conversion of 60’ Sgns Rail Wagons: a Cost Effective Solution for Transport of Lightweight Spent Fuel Flasks
Type:PATRAM Proceedings
Author(s):Michel Zachar
Abstract:
PowerPoint Presentation
Corrosion Behaviour of Borated Aluminium Used as Neutron Absorber*
Type:PATRAM Proceedings
Author(s):R. Emmerich, W. Ensinger, B. Enders
Abstract:
The electrochemical behaviour of pure and borated aluminium was examined. Measurements were performed in two different electrolytes at 90°C…
Corrosion Protection of Containers for Radioactive Waste – Storage Requirements –
Type:PATRAM Proceedings
Author(s):Axel J. Schmidt, Günter Hasemann, Friedel Vollmer
Abstract:
Radioactive waste must be handled and stored in a controlled manner. The cask/container is an important barrier for retaining the…
Criticality Assessment of Fuel Assemblies with Missing Fuel Rods An intractable Problem?
Type:PATRAM Proceedings
Author(s):Franz Hilbert
Abstract:
In current certificates of package approval the arrangement of water and guide tubes within the array of fuel rods of a fuel assembly is…
Criticality evaluation of BWR MOX fuel transport packages using average Pu content
Type:PATRAM Proceedings
Author(s):Christophe MATTERA, Badéa MARTINOTTI
Abstract:
Currently in France, criticality studies in transport configurations for Boiling Water Reactor Mixed Oxide fuel assemblies are based on…
Criticality Safety of Spent Fuel Casks Considering Water Inleakage
Type:PATRAM Proceedings
Author(s):Nancy L. Osgood, Carl J. Withee, Earl P. Easton
Abstract:
A fundamental safety design parameter for all fissile material packages is that a single package must be critically safe even if water…
CURING TIME EFFECT ON THE FRACTION OF 60Co FROM CEMENT MATRIX
Type:PATRAM Proceedings
Author(s):Ilija B. Plecas
Abstract:
Cement has been successfully used in Radioactive Waste Management to immobilize a wide range of waste including filter sludges, ion-…
Current & Proposed Revisions, Changes, & Modifications to American Codes & Standards to Address Packaging, Handling, & Transportation of Radioactive Materials & How They Relate to Comparable International Regulations
Type:PATRAM Proceedings
Author(s):William H. Borter, Carl H. Froehlich
Abstract:
This paper addresses current and proposed revisions, additions, and modifications to American Society of Mechanical Engineers (ASME) Boiler…
Customer Satisfaction Techniques Applied to the Transport of Nuclear Fuels to meet ISO 9001:2000 Requirements
Type:PATRAM Proceedings
Author(s):G.K. Fisher
Abstract:
Understanding the needs of potential and existing customers is seen as essential to the continuing success of the nuclear fuel transport…
Decrease of reaction force of metal gaskets just after initial tightening
Type:PATRAM Proceedings
Author(s):H. Akamatsu, Jun Shimojo, K. MANTANI, K. MORIKAWA, H. Taniuchi, Da YOKOE
Abstract:
The decrease of reaction force of some metal gaskets inserted into the test flange at room temperature, 120o C(real cask temperature) and…
Demonstration of freedom from brittle fracture – Validation of the Master Curve Methodology for Deriving Material Fracture Toughness
Type:PATRAM Proceedings
Author(s):Frank Norton, Henryk Pisarski
Abstract:
ASTM A 350 LF5 steel is used in the manufacture of transport flasks. In order to satisfy regulatory requirements for demonstrating this…
Demonstration of Impact Performance of the Nuclear Transport Package in On-Site Hypothetical Collision Scenarios by a Heavy Goods Vehicle
Type:PATRAM Proceedings
Author(s):Chi-Fung Tso, Conrad Izatt
Abstract:
Spent fuel modules are contained in Module Removal Container (MRC) during on-site transport at the D154 facilities in the Devonport Naval…
Demonstrative Drop Tests of Transport and Storage Full-Scale Canisters with High Corrosion-resistant material
Type:PATRAM Proceedings
Author(s):Koji Shirai, Toshiari Saegusa
Abstract:
The concrete modular dry storage technologies are becoming widely-used, aiming at better economic performances. In 1997, we commenced a…
Denial of Shipments – Myth or Reality
Type:PATRAM Proceedings
Author(s):Marc-André Charrette, David McInnes
Abstract:
The global healthcare community depends on shipments of radioisotopes. MDS Nordion manufactures and distributes radioisotopes used in the…
Design concept for maximized use of recycled scrap in the production of storage packages
Type:PATRAM Proceedings
Author(s):D. Bounin, W. Kleinkröger, D. Schreiber
Abstract:
In the decommissioning of nuclear plants large quantities of radioactively contaminated waste metal have to be disposed of. An economic…
Design of a New MOX Powder Transport Packaging to Support FBR Cycle Development Mission
Type:PATRAM Proceedings
Author(s):K. YAMAMOTO, K. Shibata, Y. Ouchi, T. Kitamura, Yoshikazu Kamino, T. Take
Abstract:
The Japan Nuclear Cycle Development Institute (JNC), which plays a leading role in research and development for the Fast Breeder Reactor (…