Research Reactor Fuel Management 6 (RRFM 2002)

دسته بندی: انرژی
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تعداد صفحات: 246 
زبان: English 
فرمت فایل : PDF (درصورت درخواست کاربر به PDF، EPUB یا AZW3 تبدیل می شود) 
حجم فایل: 16 مگابایت 

قیمت کتاب (تومان) : 33,000

European Nuclear Society, 2002. — 246 p.
6th International Topical Meeting on Research Reactor Fuel Management March 17 to 20, 2002, Ghent, Belgium. Session 1: Fissile materials supply Past and present Supply of enriched Uranium for Research Reactors in the European Union
H. Moller, RWE NUKEM GrnbH, Germany
A new Standard Specification for Uranium Metal intended for Research Reactor Fuel Fabrication
J. Laucht, RWE NUKEM GmbH, Germany
The revised IAEA Regulations and their Impact on the Transport of Research Reactor Fuel
R. Christ, F. Hilbert and M. KObel, NCS GmbH, Germany Session 2 Fuel development, qualification, fabrication and licensing RERTR Progress in MO-99 Production from LEU (Invited Paper) G.F. Vandegrift, C. Conner, S. Aase, A. Bakel, D. Bowers, E. Freiberg, A. Gelis, K.J. Quigley, and J.L. Snelgrove, Argonne National Laboratory, USA
An Update on the LEU Target Development and Conversion Program for the Maple Reactors and new Processing Facility (invited Paper) G.R. Malkoske, MIDS Nordion, Canada
Experimental Irradiation of UMo Fuel: Pie Results and Modeling of Fuel Behaviour A. Languille, D. Plancq, F. Huet, B. Guigon, CEA Cadarache, France; P. Lemoine, P. Sacristan, CEA Saclay, France; G. Hofman, J. Snelgrove, J. Rest, S. Hayes, M. Meyer, Argonne National Laboratory, USA; H. Vacelet, CERCA Framatome, France; E. Leborgne, Technicatome, France; G. Dassel, NRG Petten, The Netherlands
Status as of March 2002 of the UMo Development Program JM. Harny, Framatome-ANP; A. Languille, B. Guigon, CEA, Cadarache; P. Lemoine, CEA Saclay; C. Jarousse, CERCA, Framatome-ANP; M. Boyard, Technicatome; JL. Emin, COGEMA; France
Advances and Highlights of the CNEA Qualification Program as High Density Fuel Manufacturer for Research Reactors P. Adelfang, L. Alvarez, N. Boero, R. Calabrese, P. Echenique, M. Markiewicz, E. Pasqualini, G. Ruggirello and H. Taboada, Comisi6n Nacional de Energfa At6mica (CNEA), Argentina
Status of the Qualification Program for atomized U-Mo Dispersion Rod Type Fuel in Korea C.K. Kim, K.H. Kim, J.M. Park, D.S. Sohn, Fuel Design Technology Development Dept., K.H. Lee, H.T. Chae, HANARO Center, Korea Atomic Energy Research Institute, Korea
Progress in Development of Low-Enriched U-Mo Dispersion Fuels G.L. Hofman and J.L. Snelgrove, Argonne National Laboratory, Argonne, USA S.L. Hayes and M.K. Meyer, Argonne National Laboratory, Idaho Falls, USA
MTR Fuel Plate Qualification Capabilities at SCK-CEN E. Koonen, P. Jacquet, SCK-CEN, Belgium Session 3 Reactor operation, fuel safety and core conversion Progress of the RERTR Program in 2001 (invited Paper) A. Travelli, Argonne National Laboratory, USA
Progress of the Russian RERTR Program: Development of new-type Fuel Elements for Russian-built Research Reactors (invited Paper) A.V. Vatulin, Y.A. Stetskiy, V.A. Mishunin, V.B. Suprun, I.V. Dobrikova, VNIINM, Russia
Use of Highly Enriched Uranium at the FRM-11 (invited Paper) K. Boning, Technische Universitet Munchen, Germany
Characteristic Differences of LEU and HEU Cores at the German FRJ-2 Research Reactor R. Nabbi, J. Wolters and G. Damm, Research Center Julich, Germany
A preliminary Study on the Suitability of High Density LEU Fuel Elements to maintain BR2 Reactor Operational Characteristics A. Beeckmans and E. Koonen, SCK-CEN, Belgium
Behaviour of UMo with Cladding Failure UMUS test in the HFR J. Guidez, S. Casalta, JRC Petten, The Netherlands; F.J. Wijtsma, G. Dassel, P.M.J. Thijssen, NRG Petten, The Netherlands; C. Jarousse, CERCA Framatome, France; A. Languille, CEA Cadarache, France
Best Safety Practices for the Operation of Research Reactors H. Bock, M. Villa, Atominstitute of the Austrian Universities, Austria Session 4 Spent fuel management, corrosion and degradation Influence of the Fuel operational Parameters on the Aluminium Cladding Quality of Discharged Fuel
S. Chwaszczewski, W. Czajkowski, E. Borek-Kruszewska, Institute of Atomic Energy, Poland
MIR Reactor Fuel Assemblies Operating Experience A.F. Grachev, A.L. lzhutov, A.E. Novosyolov, M.N. Svyatkin, Z.I. Chechetkina, V.V. Aleksandrov, State Scientific Centre of Russia Research Institute of Atomic Reactors, Russia
New Storage Mode for spent Fuel at the Budapest Research Reactor T. Hargitai, I. Vidovszky, KFKI Atomic Energy Research Institute, Hungary
Storage, Inspection and SIP Testing of spent nuclear fuel from the HIFAR Materials Test Reactor
H. Selwyn, R. Finlay, P. Bull and A. Irwin, ANSTO, Australia Session 5: Back-end options and transportation Progress of the United States Foreign Research Reactor spent Nuclear Fuel Acceptance Program (invited Paper) D.G. Huizenga, M. Clapper, U.S. Department of Energy and A.W. Thrower, Science Applications International Corporation, USA
Management of the Acceptance Process of RTR Aluminide Type Spent Fuel P. Auziere, J. Thomasson, COGEMA, France
Development of Melt Dilute Technology for Disposition of Aluminium based spent Nuclear Fuel
W.F. Swift, Westinghouse Savannah River Company, USA
Spent Fuel Management Plans for the FiR 1 Reactor S.E.J. Salmenhaara, Technical Research Centre of Finland, Finland
The Russian Federation Legislation. The new Laws. Prospects for International Cooperation. A.Ye. Lebedev, Tenex, Russia Posters In-Reactor Behaviour of centrifugally atomized U3S! Dispersion Fuel irradiated up to high burn-up for HANARO K.H. Kim, D.G. Park, C.S. Lee, S.J. Oh, C.K. Kim, Korea Atomic Energy Research Institute, Korea
Boro Silicate Glass: The proven Conditioning of RTR Ultimate Waste
0. Bartagnon and V. Petitjean, COGEMA, France
Consortium NCS/GNS: Disposal of spent Nuclear Fuel from the DKFZ (Heidelberg, Germany) R. Vallentin, GNS; B. JOnger, DKFZ; T. Schmidt, NCS, Germany
U.S. Spent Nuclear Fuel Acceptance Policy 2006 and beyond J. Edlow and K.R. Brown, Edlow International Company, USA
MR-6 Type Fuel Elements cooling in natural Convection Conditions after the Reactor shut down
K. Pytel, W. Bykowski, A. Moldysz, Institute of Atomic Energy, Poland
Encapsulation Technology of MR6 spent Fuel and Quality Analysis of the EK-10 and WWR-SM spent Fuel stored more than 30 years in wet Conditions E. Borek-Kruszewska, W. Bykowski, S. Chwaszczewski, W. Czajkowski, M. Madry, Institute of Atomic Energy, Poland
Study on HANARO Core Conversion using U-Mo Fuel K.H. Lee, C.S. Lee, C.G. Seo, SJ Park and H. Kim, Research Reactor Analysis Dept., and C.K. Kim, Fuel Design Techn. Devel. Dept., Korea Atomic Energy Research Institute, Korea
Study on possibly Usage of 36 or 20 % enriched U02 TWR-S Fuel Type at RB Heavy Water Critical Assembly M. Pesic, N. Dasic and V. jubenov, The VINCA Institute of Nuclear Sciences, Yugoslavia
Powder Production of U-Mo Alloy, HIVID Process (Hydriding-Milling-Dehydriding) E.E. Pasqualini, J. Helzel Garcfa, M. L6pez, E. Cabanillas and P. Adelfang, Comision Nacional de Energia Atomica, Argentina
Improvements in irradiated Fuel Handling at Dhruva for enhanced Safety H. Gujar and S.
Agarwal, Dhruva, Bhabha Atomic Research Centre, India
Examination of U-9 % Mo Alloy Powder Microstructure in its initial Condition and after Fuel Pin Fabrication R.Kh. Gibadullin, A.D. Karpin, Yu.M. Pevchikh, V.V. Popov, V.N. Sugonyaev, V.M. Troyanov, Institute for Physics and Power Engineering, Russia
Study of in-Reactor Creep in the Alloys employed as Structural Materials for Research Reactor Core Components and Fuel Pins M.G. Bulkanov, A.S. Kruglov, Yu.M. Pevchikh, V.V. Popov, V.M. Troyanov, Institute for Physics and Power Engineering, Russia
Management and Inspection of Integrity of spent Fuel from IRT Mephi Research Reactor
V.G. Aden, S.Yu. Bulkin, A.V. Sokolov, Research and Development Institute of Power Engineering, and A.V. Bushuev, A.F. Redkin, A.A. Portnov, Moscow State Engineering Physics Institute - Technical University, Russia
Monte Carlo Simulation of Irradiation of IVITR Fuel Plates in the BR2 Reactor using a full-scale 3-D Model with inclined Channels V.V. Kuzminov, E. Koonen and B. Ponsard, SCK-CEN, Belgium
Neutronic Design of the RSG-Gas'Silicide Core T.M. Sembiring,
1. Kuntoro, and H. Hastowo, BATAN, Indonesia
Spent Fuel Management and Site exploitation at IFIN-HH, Bucharest-Magurele C.A. Dragolici, A. Zorliu, C. Petran and
1. Mincu, National Institute of Research and Development for Physics and Nuclear Engineering'Horia Hulubei' IFIN-HH, Romania
Fuel Management Optimization for the WWR-M Research Reactor in Kiev Y.P. Mahlers, Institute for Nuclear Research, Ukraine