Развитие физико-технических основ трансмутации долгоживущих радиоактивных отходов ядерных реакторов
Диссертация
В Главе 6. «Радиологическая цена трансмутации» вырабатывается подход к анализу радиологических последствий трансмутации долгоживущих отходов. Важно отметить, что конечной целью и результатом трансмутации является уничтожение причины, способной вызвать выход радиации из хранилища в глубоких геологических пластах. Однако, трансмутация неизбежно влечет за собой необходимость обращения с токсичными… Читать ещё >
Содержание
- ГЛАВА 1. Проблема трансмутации отходов
- 1. 1. Состав отработанного топлива из реакторов деления
- 1. 2. Классификация радиологической опасности
- 1. 2. 1. Токсичность
- 1. 2. 2. Риск
- 1. 2. 3. Концепция радиоактивного бремени (burden index)
- 1. 3. Выгоды от искусственной трансмутации
- 1. 3. 1. Трансмутация для облегчения глубокого подземного 31 захоронения
- 1. 3. 2. Трансмутация для снижения риска несанкционированного 37 распространения ядерных материалов
- 1. 3. 3. Трансмутация для подхода к гармоничной ядерной 41 энергетической системе
Список литературы
- Kyoto Protocol to the United Nations Framework Convention on Climate Change. -1997. — Available from: http://www.law.pace.edu/env/energy/KvotoProtocol.html
- The New Millennium A New Era for Nuclear. // Nuclear News. — 2001. — No. 1. -p.44.
- Benedict M., Levi H., Pigford T. Nuclear Chemical Engineering. / New York: McGraw-Hill Book Company. 2-nd Edition, 1981.
- Baetsle L. et al. Impact of Advanced Fuel Cycles and Irradiation Scenarios on Final Disposal Issues. / Proc. Int. Conf on Future Nuclear Systems, GLOBAL'99. -Jackson Hole, Wyoming, August 29- September 3, 1999. p.234.
- Croff A. ORIGEN2 A Revised and Updated Version of the Oak Ridge Isotope Generation and Depletion Code, ORNL-5621. — Oak Ridge National Laboratory. -1980.
- USNRC, SCALE 4.4: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation.
- Hebel L. et al. Report to the American Physical Society by the Study Group on Nuclear Fuel Cycles. // Rev.Mod. Phys. 1978. — No. l, Part II. — p.50.
- Inhalation and Ingestion Data for Workers, IAEA, Radiation and Waste Safety Division. Available fromhttp://www.iaea.org/rasanet/information/workersindex
- Apse V., Artisyuk V., Chmelev A., Takibaev A., Saito M. Transmutation of Zr-93 in High-Flux Blanket of Fusion Neutron Source. // Journal of Nuclear Science and Technology. 2000. — v.37, № 10. — p.870.
- Pigford T. Actinide Burning and Waste Disposal. / Proc. Int. Conf. Next Generation of Nuclear Power Technology. Berkley, University of California, 5 October, UCB-NE-4176 -1990. — p.532.
- Pigford T. Effect of Actinide Burning on Risk from High-Level Waste. / Trans. Amer. Nucl. Soc.- 1991. 63, p.80.
- Bush R. et al. The Potential of Partitioning and Transmutation Strategies on the Environmental Impact of High Level Waste Disposal. / Proc. of Intern. Conf. On Future Nuclear Systems GLOBAL'97. Yokohama, Japan, October 5−10. — 1997. -p. 993.
- Pigford T. Waste Transmutation and Public Acceptance. / Trans. Amer. Nucl. Soc. -63.- 1991.-p.355.
- ArieK., Endo H., Fujii-e Y., Suzuki M. An Evaluation Function for a Self-Consistent Nuclear Energy System. / Trans. Amer. Nucl. Soc. -1993. 69, p.353.
- Arie K., Kawashima M., Igashira M., Shimizu A., Suzuki M., Fujii-e Y. A Core Concept for the Self-Consistent Nuclear Energy System Based on the Promising Future Technology. / Progress in Nuclear Energy. 1995. — v.29, p.455.
- Suzuki M. Materials presented at 1993 ANS Winter Meetin. San Francisco, California, Private Communication. — 1993. — p.264.
- Croff A. et al. A Reexamination of the Incentives for Actinide Burning / Trans. Amer. Nucl. Soc. 1990. — v.62, p.76.
- The Code of Federal Regulations. Title 10, Part 60. — Disposal of High-Level Radioactive Wastes in Geologic Repositories. — Available from: http://www.nrc.gov/NRC/CFR/PART060/
- Ahn J. Relationship Between Nuclear Fuel Cycle Parameters and HLW Repository Performance. / International Seminar on Advanced Nuclear Energy Systems Toward Zero Release of Radioactive Wastes. Susono, Shizuoka, Japan. — Nov.6−9, 2000. -p.153.
- Pigford T., RasmussenN. Transmutation of Radioactive Waste: Effect on the Nuclear Fuel Cycle. / Proc. International symposium on Nuclear fuel cycle andreactor strategies: adjusting to new realities. Vienna, 3−6 June, 1997. — IAEA-TECDOC-990.
- A Roadmap for Developing Accelerator Transmutation of Waste (ATW) Technology. / A Report to Congress, October 1999. DOE/RW-0519.
- Salwatores M. Transmutation: Issues and Perspectives After a Decade of Revival. / International Seminar on Advanced Nuclear Energy Systems Toward Zero Release of Radioactive Wastes. Susono, Shizuoka, Japan, Nov.6−9, 2000. — S3−3.
- Tommasi J. et al. Synthesis of fast reactor capabilities to burn long-lived nuclear waste. / Proc. of Intern. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems, GLOBAL'95. Versailles, France, September 11−14, 1995. — p.786.
- Kusters H. et al. The nuclear fuel cycle for transmutation: a critical review. / Proc. of Intern. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems, GLOBAL'95. Versailles, France, September 11−14, 1995. — p.1076.
- KochL. et al. Nuclear Material Safeguards for P&T. / Proc. Int. Conf on Future Nuclear Systems, GLOBAL '97. Yokohama, Japan, October 5 -10, 1997. — p.876.
- IAEA Information Circular. INFCIRC/254/Rev.2/Part. — 1995. — Available from: http://www.iaea.org/worldatom/Documents/Infcircs/Others/inf254r2pl.shtml
- Wakabayashi T. Concept of Advanced Fuel Recycle System. / Proc. of 1999- JNC Intern. Forum on the Peaceful Use of Nuclear Energy. Nadao Hall, Shin-Kasumigaseki Bldg, Tokyo, Japan, February 22−23, 1999. — p.274.
- Khalil H. United Sates National Program on Actinide Recycle. / Proc. of a Specialist Meeting on the Use of Fast Reactors for Actinide Transmutation. -Obninsk, Russia, 22−24 September, 1992. IAEA-TECDOC-693. — p.21.
- Lopatkin A., Orlov V. Fuel Cycle of BREST-1200 with Non-Proliferation of Plutonium and Equivalent Disposal of Radioactive Waste. / Proc. Int. Conf on Future Nuclear Systems, GLOBAL'99. Jackson Hole, Wyoming, August 29-September 3, 1999.-p.318.
- Heizing-Goodman C. An Evaluation of the Plutonium Denaturing Concept as an Effective Safeguards Method. // Nuclear Technology. 1980. — v.50, p.242.
- WidlerP. et al. A Uranium-Plutonium-Neptunium Fuel Cycle to Produce Isotopically Denaturated Plutonium. // Nuclear Technology. -1980. v.49, p. l 15.
- Massey J., Schneider A. The Role of Pu-238 in Nuclear Fuel Cycles. // Nuclear Technology. 1982. — v.56, p.55.
- IAEA: «Innovation» Project to Find Future Paths for Nuclear. // Nuclear News. -2001. v.44, No. L-p.63.
- Shibata K. et al. Curves and Tables of Neutron Cross-Sections in JENDL-3.2. // JAERI-Data/Code, 97−003, Part II.
- Apse V., Artisyuk V., Chmelev A., Nikitin K., Saito M. An approach to long-life PWR core with advanced U-Np-Pu fuel. // Ann. of Nucl. Energy. 1999. — v.26, No.ll.-p.1021.
- Шмелев А.Н. и др. Концептуальное исследование МОХ-топливного цикла легководных реакторов с элементами защиты от распространения расщепляющихся материалов. // Известия вузов. Ядерная энергетика. 1995. -No.4, — С. 34.
- Sekimoto H., Takagi N. Preliminary study of future society in nuclear quasi -equilibrium. // Journal of Nuclear Science and Technology. 1991. — No.28. — p. 941.
- Arie К., Endo H., Fujii-e Y. An Approach to Self-Consistent Nuclear Energy System. // Trans. Amer. Nucl. Soc. -1992. No.66. — p.342.
- Adamov E., Ganev I., Orlov V. Attainment of Radiation Equivalency in Nuclear Power Radioactive Product Management. // Nuclear Technology. 1993. — 104, p.233.
- Salvatores M., Slessarev I., Uematsu M. Global Physics Approach to Transmutation of Radioactive Nuclei. // Nucl. Sei. Eng. 1994. — v. l 16, p.l.
- Apse V. et al. Enhancement of LWRs MOX-Fuel Cycle Proliferation Resistance by Plutonium Denaturing. / Proc. Int. Specialists Meeting on Future Nuclear Systems and Fuel Cycle Options, Japan, Oct. 13, 1997. p. 121.
- Fijii-e Y., Shimizu A. Self-Consistent Nuclear Energy System. // Progress in Nuclear Energy. 1995. — v.29, p.25.
- Fujita R. et al. An Application of Metal Fuel Cycle Technology Toward Self-Consistent Nuclear Energy System (SCNES) Concept. // Progress in Nuclear Energy. 2000. — v.37, p. 169.
- Fujimura K. Feasibility Study of Large MOX Fueled FBR Core Aimed at the Self-Consistent Nuclear Energy System. // Progress in Nuclear Energy. 2000. — v.37, p.177.f 52.1keda K. et al. Feasibility Study of Nitride Fuel Core and Recycle System Toward
- Self-Consistent Nuclear Energy System. // Progress in Nuclear Energy. 1998. -v.32, p.673.
- Salvatores M., Slessarev I., Uematsu M. Physics Characteristics of Nuclear Power Systems with Reduced Long-Term Radioactivity Risk. //Nucl.Sci and Engineering. 1995. — v. l20,p.l8.
- Akatsuka H. et al. Scientific Feasibility of Incineration in SCNES. // Progress in Nuclear Energy. 1995. — v.29, p.477.
- Fijii-e Y., Ohsaki T. Development of Methodology to Evaluate Equilibrium Inventory of FPs Confined in FBR. / Proceedings of Fall Meeting of the Atomic Energy Society of Japan, Part-II, 1996. A-56, p.245.
- Arie K. et al. Long-Lived FP Burning Based on the Actinide Recycle Metal Fuel it Core. // Progress in Nuclear Energy. 1998. — v.32, p.665.
- Salvatores M., Slessarev I., Thistyakov A. The Transmutation of Long-Lived Fission Products by Neutron Irradiation. // Nucl. Sci and Engineering. 1998. -v.130, p.309.
- Salvatores M. Transmutation: Issues and Perspectives after a Decade of Revival. / International Seminar on Advanced Nuclear Energy Systems Toward Zero Release of Radioactive Wastes. Susono, Shizuoka, Japan, Nov.6−9, 2000. — S3−3.
- Salvatores M. Transmutation and Innovative Options for the Back-End of the Fuel Cycle. / Proc. Int. Conf on Future Nuclear Systems, GLOBAL'99. Jackson Hole, Wyoming, August 29- September 3, 1999. — p.413.
- Taube M. The Transmutation of Strontium-90 and Cesium-137 in a High-Flux Fast Reactor with a Thermalized Central Region. // Nucl.Sci. Eng. 1976. — v.61, p.212.
- Wootan D. et al. A Comparative Assessment of the Destruction of Selected Fission Products in Fast and Thermal Reactors. / Proc. Inter. Conf. on Design and Safety of Advanced Nuclear Power Plants. -1992. p.3.7−2.
- Takahashi H. Transmutation of High-Level Radioactive Waste by a Charged Particle Accelerator. //Nucl. Technol. 1995. — v. lll, p. 149.
- Davidson J., Parish T. Reduction in the Toxicity of Fission Product Wastes Through Transmutation With Deuterium-Tritium Fusion Neutrons. // Nucl. Techn. 1980. -v.47, p.324.
- Kase T. et al. Transmutation of Cs Using Muon Catalyzed Fusion. // Muon Catalyzed Fusion. 1990. — v.5/6, p.521.
- Apse V., Artisyuk V., Chmelev A., Saito M. Transmutation of Elemental Cesium. / Proc. Int. Conf on Future Nuclear Systems, GLOBAL '99. Jackson Hole, Wyoming, August 29- September 3, 1999. — p.354.
- Artisyuk V., Chmelev A., Saito M. Multi-Component Self-Consistent Nuclear Energy System: On Proliferation Resistance Aspect. / 2-nd Annual JNC1. ternational Forum on the Peaceful Use of Nuclear Energy -For Creation of New
- Concept Toward The Nuclear Cycle. Nadao Hall, Shin-Kasumigaseki Bldg., Tokyo,
- Japan, February 21−22, 2000. p.87.
- Apse V., Artisyuk V., Chmelev A., Saito M. Transmutation Characteristics of Problematic Radionuclides in Spallation and Fusion Neutron Source. // Progress in Nucl. Energy. 2000. — v.37, p.345.
- Apse V., Artisyuk V., Chmelev A., Saito M. 244 Cm Transmutation in Accelerator-Driven System. // J. of Nucl. Sei. Technol. 1999. — v.36, p. l 135.
- Chmelev A. et al. On the Main Objectives of Transmutation Cycles for Long-Lived Fission Products and Minor Actinides. // Progr. in Nucl. Energy. 2000. — v.37, p.235.
- JENDL 3.2. Available from: JAERI Nuclear Data Center, http://wwwndc.tokai.jaeri.go.jp/jendl/j32/Tabsigs/Csl37.HTML.http://wwwndc.tokai.jaeri.go.jp/jendl/j32/Tabsigs/Sr090.HTML.1
- Kase T. et al. Transmutation of Cs Using Muon-Catalyzed Fusion Reaction. // Muon Catalyzed Fusion. 1990. — v.5/6, p.521.
- Cierjacs S. et al. High-Intensity Fast Neutron Sources and Neutrons Fields for Fusion Technology and Fusion Material Research. // Nuclear Science and Engineering -1990. v. 106, p.99.
- Asano Yu. et al. Study on Nuclear Fuel Reprocessing System Based on the Precipitation Method in Mild Aqueous Solutions. // Nuclear Technology. 1997. -v.120, p.198.
- Jarzemba M. Estimating Heat Generation Rates for Wastes Contaminated primarily by 137Cs and 90Sr. // Nuclear Technology. 1998. — v.124, p.82.
- Artisyuk V., Chmelev A., Fujii-e Y., Korovin Yu., Saito M., Suzuki M. Contribution of External Neutron Sources in Excess Neutron Generation. // Kerntechnik. 1998. — v.63, p.255.
- Барашенков B.C., Конобеев А. Ю., Коровин Ю. А., Соснин B.H. Программный комплекс «CASCADE/INPE // Атомная энергия. 1999. — т.87 — С. 283.
- Waters L. ed. MCNPX User’s Manual, Rev 0, LA-UR 99−6058, LANL, Nov. 14, 1999.
- Beard C., Belyakov-Bodin V. Comparison of Energy Deposition Calculations by LAHET Code System with Experimental Results. // Nucl. Sei. Eng. 1995. — v. 119, p.87.
- Rubbia C. et al. CERN-Group Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier. // In the Status Report Accelerator Driven Systems: Energy Generation and Transmutation of Nuclear Waste. 1997. — IAEA-TECDOC-985.
- Герасимов A.C., Киселев А. Научные и технические проблемы при создании электро-ядерных систем для трансмутации и производства энергии, опыт России // Физика атомных ядер и ядерных частиц 32. 2001. — № 1. — С. 143.
- Takizuka T. JAERI Accelerator Driven system Project. // In the Status Report Accelerator Driven Systems: Energy Generation and Transmutation of Nuclear Waste. 1997. — IAEA-TECDOC-985.
- Capiello M. The Fluidized Bed Spallation Target. /'Proc. Third International Topical Meeting on Nuclear Applications of Accelerator Technology. Long Beach, CA, November 14−18, 1999. — p.53.
- Artisyuk V., Fujii-e Y., Saito M., Suzuki M. The Potential of Accelerator- Driven Core in a Self-Consistent Nuclear Energy System. // Kerntechnik. 1996. — v.61, p.106.
- Serber R. The Production of High Energy Neutrons by Stripping. // Phys. Rev. -1947. v.72, p.1008.
- Grand P. et al. An Intense Li (d, n) Neutron Radiation Test Facility for Controlled Thermonuclear Reactor Material Testing. // Nucl. Techn. 1976. — v.29, p.327.
- Kondo T. et al. High-Energy/Intensity Neutron Facilities for Testing Fusion Materials. // Fusion Eng. and Des. 1993. — v.22, p. 117.
- Lawrence G. et al. A High-Flux Accelerator-Based Neutron Source for Fusion Technology and Material Testing. // Journ. of Fus. Energy. 1989. — v.8, p.201.
- Mann T. et al. Neutrons from D+Li and FMIT Irradiation Environment. / Report of Hanford Engineering and Development Laboratory. November 1981. — HEDL-TC 1459.
- Адо Ю.М. и др. Нейтронный генератор. Сертификат на авторское право № 435 725, 1974, Март 14, Бюллетень изобретений No. 1 1978. — С.227.
- AdoYu. et al. Neutron Production by Deuteron-Deuterium Interaction in a Gas Target. //Kerntechnik. 1991. — v.56, p. 191.
- Адо Ю.М. и др. Повышение эффективности производства нейтронов в накопительном кольце дейтронов для трансмутации радионуклидов. // Атомная энергия. 1992. -т.73, С. 289.
- Artisyuk V., Avdeev E., Konobeev A., Korovin Yu., Saito M., Suzuki M., Stankovskiy A. Intensive 14 MeV Neutron Source Based on Deuteron Storage Ring. // Progr. in Nucl. Energy. 1998. — v.37, p.457.
- Breimester J. MCNP A General Monte-Carlo Code, Version 4-A, LA-12 625-M. -Los Alamos National Laboratory. — 1993.
- Kosako K., Maekawa H., Maekawa F., Oyama Y., Uno Y. FSXLIB-J3R2: A Continuous Energy Cross-Section Library for MCNP Based on JENDL 3.2, JAERI-Data/Code 94−020. 1994.
- Artisyuk V., Chmelev A., Saito M. Neutron Excess Generation by Fusion Neutron Source for Self-Consistency of Nuclear Energy System. // J. of Nucl. Sci. Technol. 1999. — v.36, p.560.
- Kammash T. Fusion Reactor Physics. Principles and Technology. / Ann Arbor Science Publ.Inc. 1973.
- Gohar Y. et al. ITER Blanket Design. // Fus. Eng. and Des. 1995. — v.27, p.52.
- Bertoliny E. Impact of JET Results and Engineering Development on Definition of ITER Design Concept. // Fus. Eng. and Des. 1995. — v.27, p.27.
- Artisyuk V., Chmelev A., Fujii-e Y., Saito M., Suzuki M. Potential of Neutron Excess Generation by DD Fusion in SCNES. / Progr. in Nuclear Energy. 1997. -v.32, p.721.
- Momota Y. Feasibility of advanced fuel. // Trans, of Fus. Tech. 1995. — v. 27, p.^
- Ponomarev L., Puzynin I., Vinnitsky S. et al. Zh.Exp.Th.Phys. 1978. — v.74, p.849.
- Petrov Yu. Muon Catalyzed Fusion. 1987. — v. l, p.351.
- Eliezer S. et al. Muon Catalyzed Fusion-Fission Reactor Driven by a Recirculating Beam. // Nuclear Fusion. 1987. — v.27, p.527.
- Petitjean C. et al. A 14 MeV High-Flux Neutron Source Based on Muon-Catalyzed Fusion- a Design Study. // Fusion Technology 1994. — v.25, p.437.
- Harada H. et al. Incineration of Radioactive Fission Products and Transuranics by Muon-Catalyzed Fusion. // Fusion Technology. 1993. — v.24, p. 161.
- Artisyuk V., Karmanov F., Ponomarev L., Saito M. CF Intense Neutron Source and Waste Transmutation. / International RIKEN Conference on Muon Catalyzed Fusion and Related Exotic Atoms. Shimoda, Japan, 22−26 April 2001.- p.435.
- Radiological and Energy Source Terms. // ITER Non-Site Specific safety Report (NSSR-2), December 1, 1997.
- Artisyuk V., ChmelevA., Korovin Yu., Saito M., Suzuki M., Zyabletsev D. 14 MeV Neutron Potential for Fission Product Transmutation. / Proc. Int. Conf on Future Nuclear Systems, GLOBAL'97. Yokohama, Japan, October 5- 10, 1997. -p.1344.
- Ferrari M. et al. ITER Reference Breeding Blanket Design. // Fus. Eng.Des. -1999. 46, p. 177.- Technical Basis for the ITER Final Design Report, Cost Review and Safety Analysis (FDR), December 19, 1997.
- Artisyuk V., Chmelev A., Saito M. High-Flux Fusion Neutron Source for Transmutation of Fission Products. / Proc. of 4-th Japan-Korea Seminar on Advanced Reactors. Tokyo Institute of Technology, October 19−20, 2000. — p.39.
- Lane J., MacPherson H., Maslan F. Fluid Fuel Reactors. // Adison-Wesley Publ., Massachusetts, USA, 1958.
- Malang S., Mattas R. Comparison of Lithium and the Eutectic Lead-Lithium Alloy, Two Candidate Liquid Metal Breeder Materials for Self-Cooled Blankets. // Fus. Eng.Des. -1995. v.27, p.399.
- Elio F. et al. Engineering design of the ITER Blanket and Relevant Research and Development Results. // Fus. Eng.Des. 1999. — v.46, p.159.
- Malang S. Limitations on Blanket Performance. // Fus. Eng.Des. -1999. 46, p.193.
- Rebut P.-H. Issues in the Development of a Commercial Fusion Reactors. // Trans, of Fusion Techn. 1995. — v.27, p.3.
- Abdou M. Exploring Novel High Power Density Concepts for Attractive Fusion Systems. // Fus.Eng.Des. 1999. — v.45, p.145.
- Akatsuka H., Ezubtchenko A., Suzuki M. Isotope Separation Methods for Self-Consistent Nuclear Energy System. // Progress in Nuclear Energy. 1998. — v.29, p.729.
- Apse V., Artisyuk V., Chmelev A., Saito M. Fusion-Driven Transmutation of Fission Product Cesium in its Elemental Form. // Journal of Nuclear Science and Technology. 2000. — v.37, p. 1024.
- Apse Artisyuk V., Chmelev A., Saito M. Transmutation of Elemental Cesium by a Fusion Neutron Source. // Nuclear Technology. 2001. — v. 133, p.213.
- Artisyuk V., Chmelev A., Saito M. High-Flux Fusion Neutron Source for
- Transmutation of Fission Products. / Proc. of 4-th Japan-Korea Seminar on Advanced Reactors. Tokyo Institute of Technology, October 19−20, 2000. — p.39.
- YoseffM. et al. Nuclear Performance of the Thin-Liquid FW Concept of the CliFF Design. / Proc.14-th Topical Meeting. Park City, Utah, October 1−19, 2000. — p.246.
- Ghoneim N., Zinkel S. Operating Temperature Windows for Fusion Reactor Structural Materials. // Fusion Eng.Des. 2000. — v.51−52, p.55.
- Giancarli L. et al. Design Requirements for SiC/SiC Composites Structural Material in Fusion Power Reactor Blankets. // Fus.Eng.Des. 1998. — v.41, p.165.
- Artisyuk V., Chmelev A., Korovin Yu., Saito M., Stankovskiy A. Accumulation and Transmutation of Spallation Products in Accelerator-Driven Core. / Proc. 10-thft Intern. Conf. on Emerging Nuclear Energy Systems, ICENES' 2000. Petten, The
- Netherlands, Sept.24−28, 2000. p.410.
- Bowman C. et al. Nuclear Energy Generation and Waste Transmutation Using an Accelerator-Driven Intense Thermal Neutron Source. // Nucl. Instr. Meth. -1992. A320, p.336.
- Daemen L., Pitcher E., Russel G. Introduction to Spallation Physics and Spallation-Target Design. / Proc. International Conference on Accelerator-Driven Transmutation Technologies and Applications. AIP 346, Las Vegas, NV 1994. -p.356.
- Artisyuk V., Saito M.6 Stankovsky A. Radiological Hazard of Long-Lived• Spallation Products. / IAEA Workshop on Advanced Nuclear Reactor and Fuel
- Cycle Concepts. USA, Argonne National Laboratory, Nov.28.-Dec.l, 2000.p.276.
- Titarenko Yu. et al. Experimental and Computer Simulation Study of
- Radionuclide Production in Heavy Materials Irradiated by Intermediate Energy Protons. / Proc. 3-rd Intern. Topical Meeting on Nuclear Application of Accelerator Technology. Long Beach, CA, Nov. 14−18, 1999. -p.364.
- Wlazlo W. et al. Isotope Production in lxA GeV 208Pb on Proton Reaction. / Proc. 3-rd Int. Conf. On Accelerator-Driven Transmutation Technology and Applications (ADTTA'99). Prague, Czech Republic, 7−11 June, 1999. — p.532.
- Titarenko Yu. et al. Cross-section for Nuclide Production in 1 GeV Proton-Irradiated 208Pb. / Phys.Rew. 2001. — p. 123.
- Park J. et al. Review of liquid metal corrosion issues for potential containment materials for liquid lead and lead-bismuth eutectic spallation targets as a neutron source. // Nucl. Eng. Des. -2000. v. 196, p.315.
- Khorasanov G. et al. Lead and Tin Targets for Reducing Polonium Waste. /
- Proc. 3-rd Int. Conf. On Accelerator-Driven Transmutation Technology and Applications (ADTT'99). Praha, Zcech Republic, 7−11 June, 1999. — p.532.
- Shvedov O. et al. ADS Program in Russia. In the Status Report Accelerator Driven Systems: Energy Generation and Transmutation of Nuclear Waste. 1997.-IAEA-TECDOC-9 8 5.
- Yefimov E. et al. Problems of Molten Lead-Bismuth Target Development for Accelerator-Driven Systems. / Proc. 3-rd Int. Conf. On Accelerator-Driven Transmutation Technology and Applications (ADTTA'99). Prague, Czech Republic, 7−11 June, 1999.-p. 134.