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DEVELOPMENT OF A NEW UNIFIED TRANSPORT PACKAGING FOR SHIPMENT OF PWR REACTOR FRESH FUEL ASSEMBLIES
Type:PATRAM Proceedings
Author(s):L.V. Barabenkova, E.I. Latypov, V.Z. Matveev, A.T. Mishustin, A.I. Morenko, M.I. Sumin, V.I. Shapovalov, Yu.V. Goncharov, A.A. Enin, V.V. Shchuchkin, A.B. Dolgov
Abstract:
The paper describes a transport packaging (TUK TK-C69) designed for transportation of fresh fuel assemblies from PWR reactor (fuel…
Development of a Packaging to Transport the new Standardised range of Disposal Canisters to a Geological Disposal Facility in the UK
Type:PATRAM Proceedings
Author(s):Peter C. Purcell, Neil Carr
Abstract:
The UK’s Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) is developing concepts to…
DEVELOPMENT OF A RANGE OF STANDARDISED DISPOSAL CONTAINERS FOR HIGH LEVEL WASTE AND SPENT FUEL DEEP DISPOSAL IN THE UK
Type:PATRAM Proceedings
Author(s):Neil Carr, Chi-Fung Tso, Conrad Izatt, Ryoji ASANO, Chris Fry, George Wright, Chris Punshon
Abstract:
The Nuclear Decommissioning Authority (NDA) has established the Radioactive Waste Management Directorate (RWMD) to manage the delivery of…
DEVELOPMENT OF AN OUTLINE OPERATING SYSTEM FOR THE UK MULTI-PURPOSE CANISTER SYSTEM FOR THE STORAGE, TRANSPORT AND DISPOSAL OF SPENT FUEL
Type:PATRAM Proceedings
Author(s):Mark Johnson, Neil Carr, Chi-Fung Tso, Conrad Izatt
Abstract:
The Nuclear Decommissioning Authority (NDA) has established the Radioactive Waste Management Directorate (RWMD) to manage the delivery of…
DEVELOPMENT OF FUNCTIONAL RADIATION SHIELDING MATERIAL
Type:PATRAM Proceedings
Author(s):Toshiaki YAMAZAKI, Yusuke Kamimura, Daisuke Nagasawa, Masayuki Moriya, Yosuke Shimada
Abstract:
In order to reduce the radiation exposure of the personnel engaged in the decontamination of the highdose regions of Fukushima, a new type…
Development of Specific Requirements for the Transport of Large Components
Type:PATRAM Proceedings
Author(s):J. Ramsay
Abstract:
There is an increasing demand in many countries for transporting large radioactive objects, such as equipment from decommissioning or…
DEVELOPMENT OF THE CRITICALITY CONTROL OVERPACK PAYLOAD CONTAINER FOR TRANSPORT OF EXCESS PLUTONIUM OXIDES IN THE TRUPACT-II AND HALFPACT PACKAGINGS
Type:PATRAM Proceedings
Author(s):Brad A. Day
Abstract:
A new transuranic (TRU) waste payload container has been developed for the shipment of a target waste stream consisting of approximately 9…
DEVELOPMENT OF TK-26, NEW GENERATION TRANSPORT AND STORAGE CASK FOR PWR SPENT FUELS
Type:PATRAM Proceedings
Author(s):Hiroaki Taniuchi, Dai Yokoe, Jun Shimojo, Hiroshi Akamatsu
Abstract:
The design of TK type transport and storage cask for BWR spent fuels such as TK-69, TK-52 are completed and the safety analysis has been…
DEVELOPMENT OF TRAINING COURSE ON TRANSPORT SECURITY OF RADIOACTIVE MATERIALS
Type:PATRAM Proceedings
Author(s):R.B. Pope, Y.Y. Liu, J. M. Shuler
Abstract:
Argonne National Laboratory (Argonne), with the support of the U.S. Department of Energy (DOE) Packaging Certification Program (PCP), is…
DEVELOPMENT, ANALYSES AND VALIDATION OF FE MODEL OF FSC 2005
Type:PATRAM Proceedings
Author(s):Chi-Fung Tso, Amar Mistry, Sundip Shah, Joerg Melzer, Gerald Tschan, Olaf Oldiges
Abstract:
Between 1986 and 2011, WAK GmbH packaged wastes from the experimental reactors at Karlsruhe research centre into about 3000 Konrad-type IV…
Differences in Provisions between Dangerous Goods Regulations and Radiation Protection Regulations for the Transportation of NORM and TENORM in Germany
Type:PATRAM Proceedings
Author(s):Markus Trautmannsheimer, Yvonne Arendt
Abstract:
The transportation of Naturally Occurring Radioactive Materials (NORM) and Technologically Enhanced Naturally Occurring Radioactive…
DISMANTLING OF THE GEORGES BESSE 1 ENRICHMENT PLANT – TRANSPORT CHALLENGES
Type:PATRAM Proceedings
Author(s):Jürgen Werle, Philippe Seurat
Abstract:
AREVA’s Georges Besse 1 enrichment plant at the Tricastin site in France has ended commercial production during early summer 2012. Whilst…
DROP TEST ANALYSIS OF 1/3 SCALE TK TYPE TRANSPORT AND STORAGE CASK
Type:PATRAM Proceedings
Author(s):Norihiro Kageyama, Hiroaki Taniuchi, Kiyoshi Takahama, Jun Shimojo, Keisuke Umehara
Abstract:
Safety of spent fuel dry storage system using casks is focused on in these days and this system is expected to be strongly increasing. The…
DROP TEST EXPERIMENTAL RESULTS OF 1/3 SCALE MODEL FOR TK TYPE TRANSPORT AND STORAGE CASK
Type:PATRAM Proceedings
Author(s):Jun Shimojo, Keisuke Umehara, Akito Oishi, Norihiro Kageyama, Hiroaki Taniuchi, Takao Shirakura
Abstract:
Dry storage system using spent fuel casks is focused on in these days and demand of storage using casks is expected to be strong…
DROP TESTING OF THE DN30 PROTECTIVE STRUCTURAL PACKAGING FOR THE TRANSPORT OF URANIUM-HEXAFLUORIDE
Type:PATRAM Proceedings
Author(s):Wolfgang Bergmann, Thomas Breuer
Abstract:
The design of the DN30 protective structural packaging (PSP) developed by DAHER-NCS for the transport of natural, enriched and reprocessed…
DROP-WEIGHT RING COMPRESSION TEST FOR EVALUATING THE MECHANICAL BEHAVIOR OF FUEL RODS UNDER IMPACT CONDITIONS
Type:PATRAM Proceedings
Author(s):Elena Torres Alvarez, Jesus Ruiz-Hervias, Miguel A. Martin Rengel
Abstract:
Several static and dynamic tests have been proposed to assess impact behaviour of spent fuel cladding. For example, the three-point bending…
Dry Interim Storage in Switzerland for 30 Years
Type:PATRAM Proceedings
Author(s):Frank Koch, Bernd Roith, Stefan Theis
Abstract:
Since Patram2010 long-term interim dry storage was introduced as a major issue to the international community. At the IAEA level several…
Dual Purpose Cask Safety Evaluation - Expertise in Dry Storage
Type:PATRAM Proceedings
Author(s):Wolfgang Botsch, Silva Smalian, Peter Hinterding
Abstract:
In Germany dual purpose casks for spent nuclear fuel (SF) or high level radioactive waste (HLW) are used for safe transportation and…
DYNAMIC IMPACT ANALYSES AND TESTS OF CONCRETE OVERPACK
Type:PATRAM Proceedings
Author(s):Sanghoon Lee, Sang-Soon Cho, Ki-Young Kim, Je-Eon Jeon, Ki-Seog Seo
Abstract:
Concrete cask is an option for spent nuclear fuel interim storage. A concrete cask usually consists of metallic canister which confines the…
EFFECT OF IMPACT POINT OFFSET OF A SOLID MILD STEEL PLATE TO THE NUCLEAR MATERIAL TRANSPORT CASK IN DROP TEST III
Type:PATRAM Proceedings
Author(s):Toshiya Kitamura, Hiroaki Doi, Kunio Maruoka
Abstract:
IAEA Safety Standards No.TS-R-1 para.727 (c) requires drop test III. To assure the integrity of a cask in drop test III, the specimen is…