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					                                PROVISIONAL PROGRAMME
                              INTERNATIONAL CONFERENCE
                          «NUCLEAR POWER AND FUEL CYCLES»
                           1-5 December 2003, Moscow-Dimitrovgrad
                          Part I (NIKIET, Moscow), 1-2 December 2003
                                         1 December 2003
830-930 Registration
930-940 Introduction by RF Minister for Atomic Energy A.Yu. Rumyantsev.
940-1830 Plenary presentations (25-30 min., including questions and answers):
1.    Nuclear in the Energy Strategy of Russia ( О.М. Saraev. “Rosenergoatom”)
2.    Potential for development and feasibility of radiation equivalence between uranium and waste in
      the future nuclear power industry (A.V. Lopatkin, NIKIET)
3.    Technology to resolve the problems of SNF and radwaste management at NPPs with a closed
      fuel cycle (V.B. Ivanov, NIIAR)
4.    Technological measures to consolidate the Nonproliferation Regime (Ye.N. Avrorin, VNIITF)
5.    Environmental safety of nuclear power and fuel cycles (L.A. Bolshov, IBRAE)
6.    Fuel resources available to nuclear power today and in the future (V.V. Shatalov, VNIIHT)
7.    Advanced and innovative projects in the REA development strategy (M.F. Rogov,
      “Rosenergoatom”)
8.    Fast reactors in the future power industry (V.V. Orlov, NIKIET)
9.    System model of Russian nuclear power (S.D. Malkin, KI)
10. Nuclear power – Ethics and dialectics (B.V. Nikipelov, Minatom)
11. Environmental risks of nuclear power (Ye.P. Ryazantsev, Kurchatov Institute, I.I. Kryshev, SIA
      “Taifun”, Russia)
12. Development of a plant with BREST-OD-300 reactor and on-site fuel cycle for the Beloyarsk
      NPP site – Acting upon President Putin’s Initiative (A.I. Filin, NIKIET)
13. Fuel cycle of BREST reactors - Solution of radwaste management and proliferation resistance
      problems. (A.G. Glazov, NIKIET)
14. On-site fuel cycle of fast reactors with pyrochemical reprocessing and fuel fabrication based on
      vibrocompaction (A.F. Grachov, NIIAR)
15. Advanced fuel cycles of power reactors with nonaqueous reprocessing of irradiated fuel (A.A.
      Mayorshin, NIIAR)
1900 Reception
                                         2 December 2003
930-1300 Plenary presentations (25 min., including questions and answers):
16.   Nuclear power complex and Energy Strategy of the Republic of Kazakhstan (T.M. Zhantikin,
      Nuclear Power Committee of the Republic of Kazakhstan)
17.   Use of МОХ fuel in today’s fast reactors (V.M. Poplavsky, FEI)
18.   Comparative analysis of nuclear power development under conditions dictated by the Energy
      Strategy and energy market (A.N. Karkhov, IBRAE)
19.   Comparison of potential hazards of U-Pu, Th-U and Th-U-Pu fuel cycles in a ternary nuclear
      power mix (A.G. Aseev, KI)
20.   Advantages of a subcritical ADS cooled by liquid heavy metal: very high fuel burnup,
      degradation of Pu isotopics (G.G. Kulikov, MIFI)
1710 Departure to Dimitrovgrad (Kazansky railway station)
                        Part II (NIIAR, Dimitrovgrad) – 3-5 December 2003
                                          3 December 2003
  00    00
15 -19 Plenary presentations (25 minutes per presentation, including questions and answers)
21.    The 25th anniversary of the on-site facility “Oryol”. Development and operation experience and
       prospects for deployment of automated remotely controlled fuel cycle facilities (V.B. Ivanov,
       O.V. Skiba, A.A. Mayorshin, A.V. Bychkov, V.A. Kislyi, NIIAR)
22.    Development and operation of “Oryol-1” facility for fabrication of BOR-60 fuel assemblies
       (O.V. Skiba. Yu.F. Ovsyannikov, A.A. Mayorshin, L.G. Babikov, S.I. Mamontov, V.A. Karlov,
       NIIAR)
23.    Development and operation of an experimental complex for fabrication of fuel assemblies
       designed for the BN-800 reactor (O.V. Skiba, Yu.F. Ovsyannikov, A.A. Mayorshin, V.A. Kislyi,
       A.P. Kirillovich, S.I. Mamontov, V.B. Mishinev, NIIAR)
24.    Equipment of the nuclear fuel cycle (B.P. Shevelin, R.S. Karimov, V.N. Guzanov, V.I. Vasiliev,
       G.A. Panov, N.G. Sergeev, V.A. Chemezov (JSC “SverdNIIkhimmash”), A.G. Glazov (NIKIET)
25.    Problems of utilising ex-weapon plutonium in an all-МОХ core of BN-600, with the fuel
       produced by vibrocompaction (B.A. Vasiliev (OKBM), Yu.F. Kolotilov (GSPI), A.A. Mayorshin
       (NIIAR), V.I. Matveev, V.M. Poplavsky, A.N. Chebeskov (FEI), N. Kawata, Т. Funada, К.
       Aratani (JNC, Japan)
26.    Development of a fuel fabrication process for the BREST-OD-300 reactor (A.V. Vatulin, V.A.
       Mishunin, A.V. Morozov, V.D. Pashkov, A.N. Fyodorov, VNIINM)
27.    Feasibility of BN-600 and BN-800 operation in a closed fuel cycle with pyroelectrochemical fuel
       reprocessing (A.A. Abagyan, Ye.F. Seleznev (VNIIAES), V.B. Ivanov (NIIAR)
28.    Advancement in FBR Fuel Recycle Development in Japan (Aiji Yamato, Shigeo Nomura, Hisao
       Ojima, Japan Nuclear Cycle Development Institute)
29.    Testing of new SNF reprocessing methods for the RT-2 Facility (V.I. Beznosyuk, B.Ya. Galkin,
       B.Ya. Zilberman, V.M. Yesimantovsky, R.I. Lyubtsev, V.F. Saprykin, Yu.S. Fyodorov, “Radium
       Institute”)

                                          4 December 2003
 00    00
9 -13 – Visit to NIIAR facilities
1500-1900 – Special Sessions (15 minutes per presentation, including questions and answers)

                 Session 1. FUEL, FUEL RODS AND FUEL CYCLE FACILITIES

30.    Pyrochemical process for granular oxide fuel production – Development experience and
       prospects (O.V. Skiba, S.K. Vavilov, Yu.P. Savochkin, L.G. Babikov, D.A. Bobrov, A.V. Bychkov,
       M.V. Kormilitsyn, NIIAR)
31.    Use of vibrocompacted oxide fuel – Experience and prospects (A.F. Grachov, A.A. Mayorshin,
       V.N. Golovanov, V.A. Tsykanov, A.V. Bychkov, O.V. Shishalov, NIIAR)
32.    Prospects for development of nonaqueous reprocessing methods and vibrocompaction process
       (A.V. Bychkov, NIIAR)
33.    Development of equipment for a closed fuel cycle involving pyroelectrochemical processing and
       preparation of granulated material for fabrication of vibrocompacted fuel (G.P. Popkov, A.V.
       Bychkov, M.V. Kormilitsyn, A.A. Mayorshin, O.V. Skiba, NIIAR)
34.    Adaptation of the OIK facility for fabrication of МОХ fuel, vibrocompacted fuel rods and fuel
       assemblies for BN-600 reactor, using weapons-grade plutonium (O.V. Skiba, A.A. Mayorshin,
       A.V. Bychkov, V.A. Kislyi, Yu.F. Ovsyannikov, D.A. Bobrov, S.I. Mamontov, P.I. Davydov, Ye.A.
       Samosenko, A.R. Shalak, NIIAR)
35.    Possibilities for plutonium utilisation in a hybrid core of BN-600 reactor, charged with
       vibrocompacted МОХ fuel (B.A. Vasiliev, O.V. Mishin, M.R Farakshin (OKBM), V.I. Matveev,
       V.M. Poplavsky, A.N. Chebeskov (FEI), A.A. Mayorshin, A.V. Bychkov, V.A. Kislyi (NIIAR),
       N. Uto, T. Mizuno, K. Aratani (JNC, Japan)

                                                                                                    2
36.   Development and irradiation of experimental fuel assemblies with mixed uranium-plutonium fuel
      (both vibrocompacted and pelletised) in BN-600 reactor (B.A. Vasiliev, S.A. Voronov, O.V.
      Mishin, T.A. Klimashina, M.R. Farakshin (OKBM), G.V. Babenko, V.V. Maltsev, V.F. Roslyakov,
      V.V. Chuev (Beloyarsk NPP)
37.   Development of ODS Ferritic Steel Cladding and its Irradiation Test in BOR-60 (T. Kaito, S.
      Ukai, M. Seki, A.A. Mayorshin, O.V. Shishalov)
38.   Experience of using recovered uranium for fabrication of fuel rods and assemblies at JSC
      “Machine Building Factory” (Ye.L. Sannikov, JSC “MSZ”)
39.   The Developments of MOX Fuel Research in China (Li Huailin, Zhou Peide, Сhina Institute of
      Atomic Energy)
40.   Development of nuclear fuel fabrication processes at JSC “UMZ” (S.A. Yashin, А.А. Kuchkovsky,
      I.V. Korobeinikov, A.V. Manych, JSC “UMZ”, Kazakhstan)
41.   Feasibility of plutonium utilisation in VVER reactors with plutonium-thorium fuel (V.M.
      Dekusar, A.G. Kalashnikov, E.N. Kapranova, V.E. Korobitsyn, Z.N. Chizhikova, FEI)
42.   Experiments to support the use of MOX fuel in commercial fast reactors (V.V. Chuev,
      A.N. Ogorodov, V.V., Maltsev, F.G. Reshetnikov, N.B. Sokolov, O.S. Korostin, Beloyarsk NPP)
43.   Results of the in-pile testing of UO2 microfuel in high-parameter water (V.A. Kuprienko, E.P.
      Klochkov, V.G. Toporova, I.G. Lebedev, Z.I. Chechetkina, NIIAR, A.V. Kotelnikov, V.S. Sineev,
      S.M. Mamykin, S.A. Buimov, Novosibirsk chemical concentrate plant)

      Session 2. SFAETY AND ECONOMICS OF NUCLEAR POWER AND FUEL CYCLES

44.   Radioecological aspects of the closed fuel cycle of BOR-60 reactor (A.P. Kirillovich, A.V.
      Bychkov, A.A. Mayorshin, M.V. Kormilitsyn, V.V. Serebryakov, NIIAR)
45.   Radiation conditions during decontamination of a pilot facility for nuclear fuel reprocessing (A.P.
      Kirillovich, A.V. Bychkov, M.V. Kormilitsyn, A.K. Pravdin, V.V. Serebryakov, NIIAR)
46.   Assessment of environmental safety of Russian nuclear plants (Yu.A. Egorov, A.L. Suzdaleva,
      (VNIIAES), B.I. Nigmatulin (ENIC), V.S. Nikolaevsky, F.A. Tikhomirov (Moscow State
      University)
47.   Environmental safety of NPPs – Management and assessment (Yu.A. Yegorov, A.L. Suzdaleva,
      VNIIAES), B.I. Nigmatulin (ENIC), V.V. Severinov (“Rosenergoatom” «)
48.   Radiation conditions around the “SHK” Complex, resulting from its activities (G.S. Andreev, A.I.
      Malyshkin. A.A. Vlasov. S.I. Bushuev, SHK)
49.   Decommissioning of production reactors at SHK (V.I. Khvostov, P.G. Savinykh, Ye.A. Komarov)
50.   Estimated economic efficiency of small nuclear heat and power plants as an option for replacing
      conventional plants by alternative energy sources in the energy mix of Belarus (S.I. Gulnik, V.T.
      Kazazyan, S.G. Mandik, A.A. Mikhalevich, B.I. Popov, S.N. Sikorin, A.P. Yakushev, OIEYaI,
      Republic of Belarus)
51.   Contribution of fuel provision (uranium ore mining) to total energy production costs at nuclear
      plants (V.G. Ivanov, VNIPIPT)
52.   Energy and power market reformation. New conditions for nuclear plant operation (A.I.
      Arkhangelskaya, V.S. Fiantsev, ”Rosenergoatom” «)
53.   Interval model for assessing investments in NPP projects in the context of uncertainty and risk
      (A.P. Voshchinin, V.M. Kupriyanov, A.V. Tyurin, N.Ye. Yakovlev (CNIIAtominform); V.I.
      Rachkov (Minatom)
54.   Public radiation hazard caused by nuclear plant operation: from tolerable to totally acceptable
      (V.P. Kryuchkov, A.V. Novikov, B.A. Bezrukov, I.V. Dolzhenkov (“Rosenergoatom” «), Ye.A.
      Ivanov (VNIIAES)
55.   Estimated contribution of Russian nuclear power to reduction of greenhouse gas emissions in
      various scenarios of the industry development (M.V. Rachkov, V.I. Usanov, A.N. Chebeskov, S.V.
      Yugai)




                                                                                                       3
          Session 3. MANAGEMENT OF SPENT FUEL AND RADIOACTIVE WASTE

56.   Prospects for developing SF management techniques (O.V. Skiba, S.K. Vavilov, Yu.P. Savochkin,
      A.V. Bychkov, M.V. Kormilitsyn, V.S. Ishunin, A.K. Pravdin, V.M. Chistyakov, NIIAR)
57.   Burning of minor actinides in the fuel cycle of fast reactors. DOVITA Code – results of a ten-
      year effort. (A.V. Bychkov, O.V. Skiba, A.A. Mayorshin, M.V. Kormilitsyn, O.V. Shishalov, I.Yu.
      Zhemkov, V.A. Kislyi, NIIAR)
58.   Treatment and immobilization of pyrochemical residues and Pu-containing waste (A.N.
      Lukinych, L.G. Babikov, Yu.G. Lavrinovich, A.V. Bychkov, NIIAR)
59.   Effect of MOX fuel reprocessing by pyroelectrochemical technique on BN physics and on
      radiation characteristics of fuel assemblies (V.A. Chernyi, A.G. Tsykunov, L.A. Kochetkov, A.I.
      Nevinitsa, G.N. Khokhlov (FEI), A.V. Bychkov, M.V. Kormilitsyn, S.K. Vavilov, L.G. Babikov
      (NIIAR)
60.   Fractioning of high-level waste using combined agent (D.N. Shishkin, B.Ya. Galkin, B.Ya.
      Zilberman, Yu. S. Fedorov, O.V. Shmidt, Radium Institute)
61.   Implementation of the dry storage technique for the spent fuel of nuclear power plants (V.I.
      Lebedev, V.N. Bespalov, Rosenergoatom)
62.   Promising treatment techniques for the liquid radioactive waste of nuclear power plants (A.A.
      Reznik , Rosenergoatom)
63.   Gas fluoride reprocessing technique for the spent fuel of light water reactors and the possibilities
      to improve it to minimise initial investments and operating costs (V.V. Shatalov, M.B. Seryogin,
      VNIIHT)
64.   Plasma technique for treatment of radioactive, hazardous, medical and household waste (I.A.
      Sobolev, S.A. Dmitriev, F.A. Lifanov, V.N. Popkov, A.E. Savkin, M.A. Polkanov, V.A. Gorbunov,
      N.A. Spirin, “Radon”)
65.   Radon experience in treatment of liquid radioactive waste (S.A. Dmitriev, F.A. Lifanov, Yu.V.
      Karlin, A.E. Savkin, “Radon”)
66.   Remote systems and dedicated manipulators for handling of radioactive waste and spent fuel
      (A.R. Amirov, N.E. Glazkin, V.V. Shvedov, “TARIS”)
67.   Standard packages for shipment and temporary storage of spent fuel as a promising tool for
      handling spent fuel (S.G. Oleinik, V.V. Vdovin, A.M. Razgildeev, ENIC)

           Session 4. ADVANCED REACTORS AND FUEL EXAMINATION TOOLS

68.   NDT system for highly active fuel (L.I. Kosarev, N.R. Kuzelev, Yu.I. Pakhunkov, E.V. Skachkov,
      V.P. Terentiev, A.S. Shtan, V.M. Yumashev, VNIITFA)
69.   Service life, safety enhancement and life extension of uranium-graphite reactors ADE-4 and
      ADE-5 (V.V. Shidlovsky, V.N. Meshcheryakov, A.A. Tsyganov, P.M. Gavrilov, A.G. Kokhomsky,
      SHK)
70.   Design and configuration of the key systems and components of the BREST-OD-300 reactor
      (A.I. Filin, V.S. Tsykunov, V.N. Leonov, A.A. Pikalov, NIKIET)
71.   Specific features of the main circulation circuit in the BREST-OD-300 reactor (A.I. Filin, V.S.
      Tsykunov, V.N. Leonov, A.G. Sila-Novitsky A.A. Pikalov, NIKIET)
72.   A concept of thermal nuclear reactor featuring complete utilization of uranium and thorium fuel
      (V.M. Kotov, L.N. Tikhomirov, Zh.A. Zhumadilova, S.V. Kotov, Kazakhstan Nuclear Research
      Center)
73.   Feasibility of small-power reactors with a pebble-bed core (P.I. Ananich, A.P. Akhramovich,
      V.T. Kazazyan, V.P. Kolos, A.A. Mikhalevich, S.N. Sikorin, N.A. Tetereva, Nuclear Research
      Institute, Belarus)
74.   Gas-cooled heavy-water molten salt reactor (V.N. Konev, M.L. Okhlopkov, V.V. Seliverstov,
      ITEF)
75.   Multipurpose small-power fast reactor SWBR-75/100 and associated fuel cycles (A.V. Zrodnikov,
      G.I. Toshinsky, O.G. Grigoriev, A.V. Dedul (FEI), Yu.G. Dragunov, V.S. Stepanov, N.N. Klimov
      (Gidropress), A.A. Mayorshin, A.V. Bychkov (NIIAR)

                                                                                                        4
76.   An advanced VVER-1000 reactor. Prospects (S.B. Ryzhov, I.N. Vasilchenko, D.N. Ermakov, A.M.
      Rogov, Gidropress)
77.   Reactors for advanced ice breakers and floating power plants for different applications (E.V.
      Goryunov, V.I. Zalugin, Yu.K. Panov, V.I. Polunichev, OKBM)
78.   Reactor facility VBER-300 for nuclear cogeneration plant, developed around marine packaged
      reactors (O.B. Samoilov, Panov Yu.K., A.V. Kurachenkov, Novikov V.V., OKBM)
79.   An innovative project GT-MGR (N.G. Kodochigov, A.V. Vasyaev, L.E. Kuznetsov (OKBM), N.N.
      Ponomarev-Stepnoi (Kurchatov Institute), V.M. Makarov (VNIINM)
80.   A vessel-type nuclear reactor with microfuel and light-water coolant under supercritical pressure
      intended for single-circuit nuclear plants (G.A. Filippov, A.A. Avdeev, R.G. Bogoyavlensky
      (VNIIAM), V.P. Bykov, E.A. Dvoinishnikov, P.A. Leppik, (Kurchatov Institute)
81.   Enhancement of safety and performance of VVER reactors using microfuel-based rods (I.I.
      Fedik, S.S. Gavrilin, V.P. Deniskin, V.I. Nalivaev (NPO"Luch"), Yu.G. Dragunov, S.B. Ryzhov,
      V.P. Spasskov (Gidropress)

                                            Poster papers

82.   Experience in using radiation introscopy and tomography tools and techniques in development of
      fuel manufacture techniques for nuclear plants (L.I. Kosarev, N.R. Kuzelev, V.M. Yumashev
      (VNIITFA); V.G. Dvoretsky, V.A. Zhigarev (NIIAR)
83.   Use of extraction technique for production of UF6 at a sublimate plant to FSTM C787
      requirements (V.V. Shidlovsky, A.S. Kozyrev, Yu.F. Kobzar, A.K. Ledovskikh, A.S. Ryabov, N.A.
      Mikhailova, M.E. Romanov, F.A. Dorda)
84.   Improvement of LRW handling at SHK to terminate waste dumping into open storage facilities
      (V.M. Kondakov, A.S. Ryabov, V.G. Balakhonov, I.V. Yurko (SHK), I.M. Kosareva, M.K.
      Savushkina (IFH)
85.   Provision of radiation and environmental safety in the areas with NPP sites (Yu.A. Egorov,
      VNIIAES)
86.   Environmental management in NPP regions as a tool for supporting environmental safety of
      NPPs (Yu.A. Yegorov, A.L. Suzdaleva, VNIIAES)
87.   Succession in the ecosystem of water reservoir used as a cooling pond for a NPP (Yu.A. Egorov,
      A.L. Suzdaleva, (VNIIAES)
88.   Current geoecological problems in NPP regions (Yu.A. Egorov, A.L. Suzdaleva, (VNIIAES)
89.   Experience in decommissioning of open storage facilities of LRW - B-2 pool (V.V. Shidlovsky,
      V.A. Matyukha, A.A. Zubkov, A.S. Kozyrev, A.S. Ryabov, N.A. Mikhailova, E.N. Semenov. (SHK),
      E.V. Zakharova (IFH)
90.   Hardware and software for continued measurement of U235 in separation cascade (V.E.
      Gorokhov, V.M. Ilyukhin (GROG)
91.   Simulation of mechanical behaviour of BREST core components (E.N. Sinitsyn, V.Yu. Sakharov,
      M.D. Dolotkazin, ENEC)
92.   Computer and regulatory codes for strength analysis of load-bearing components of absorber
      elements (S.V. Evropin, V.B. Poselsky, E.N. Sinitsyn, V.N. Demintievsky, V.Yu. Sakharov
      (ENES), V.B. Ponomarenko, M.D. Gershonyuk (MZP)
93.   Development of advanced steel casks for radioactive waste (S.G. Oleinik, V.V. Vdovin, A.M.
      Razgildeev, ENIC)
94.   Liquid membranes used in the process of LRW treatment (A.A. Kopyrin, M.A. Afonin, A.S.
      Petrov, St.-Petersburg Technical University)
95.   Studies on and development of technology for fabrication of ceramic uranium nidride (V.V.
      Shatalov, L.P. Parshin, V.P. Mashirev, S.A. Melnikov, E.N. Zvonarev, VNIIHT)
96.   A comprehensive study on the possibility of using X-ray transmission computer
      microtomography in the process of nuclear fuel development and fabrication (V.I. Lelekov,
      VNIIAM – “Impulse-Atom”)
97.   Study of nuclear processes taking place on the surface of fuel cores in light-water reactors (A.N.
      Andrianov (Minatom of Russia), V.G. Baranov, Yu.G. Godin, G.V. Tikhomirov (MIFI)
                                                                                                      5
98.  Programme of Hot Cell Work for NPP Fuel Element Research at CIAE (Ran Muzi, Сhina
     Institute of Atomic Energy)
99. Computational and experimental studies on coolant hydrodynamics in the alternative fuel
     assemblies of VVER-1000 (S.M. Dmitriev, A.E. Khrobostov, M.A. Legchanov, NGTU)
100. Economic and environmental aspects of floating and underground nuclear cogeneration plants of
     small and medium power (V.N. Dolgov, OEEP RAN, St.-Petersburg)
101. Physical and chemical foundations for pyrochemical reprocessing of fuel elements with uranium-
     aluminium compositions (A.V. Bychkov, M.V. Kormilitsyn, S.K. Vavilov, Yu.P. Savochkin, A.G.
     Osipenko, NIIAR)
102. Environmental safety of activities at the Underground Reprocessing Complex (V.V. Zhidkov,
     K.G. Koudinov, A.E. Shishlov, GHK)

                              5 December 2003, NIIAR, Dimitrovgrad
                         00
                        9 -1200 – Round-table discussion, press conference




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