Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors / Edition 1

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Overview

MOX fuel, a mixture of weapon-grade plutonium and natural or depleted uranium, may be used to deplete a portion of the world's surplus of weapon-grade plutonium. A number of reactors currently operate in Europe with one-third MOX cores, and others are scheduled to begin using MOX fuels in both Europe and Japan in the near future. While Russia has laboratory-scale MOX fabrication facilities, the technology remains under study. No fuels containing plutonium are used in the U.S.
The 25 presentations in this book give an impressive overview of MOX technology. The following issues are covered: an up to date report on the disposition of ex-weapons Pu in Russia; an analysis of safety features of MOX fuel configurations of different reactor concepts and their operating and control measures; an exchange of information on the status of MOX utilisation in existing power plants, the fabrication technology of various MOX fuels and their behaviour in practice; a discussion of the typical national approaches by Russia and the western countries to the utilisation of Pu as MOX fuel; an introduction to new ideas, enhancing the disposition option of MOX fuel exploitation and destruction in existing and future advanced reactor systems; and the identification of common research areas where defined tasks can be initiated in cooperative partnership.

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Product Details

  • ISBN-13: 9780792334736
  • Publisher: Springer Netherlands
  • Publication date: 5/31/1995
  • Series: Nato Science Partnership Subseries: 1 (closed) , #2
  • Edition description: 1995
  • Edition number: 1
  • Pages: 310
  • Product dimensions: 9.21 (w) x 6.14 (h) x 0.75 (d)

Table of Contents

Preface. 1: Nuclear Material Management. 1. Management of Plutonium in Russia; N.N. Egrov, V.M. Murogov, V.S. Kagramanian, M.F. Troyanov, V.M. Poplavski, V.I. Matveev. 2. Overview Long-Term Disposition Options for Plutonium: Rational Management of Excess Weapons Plutonium; E.R. Merz. 3. Basic Technological Solutions for Plutonium Management at the RT-2 Plant; D.N. Bykhovski. 4. Disposition of Surplus Separated Plutonium: Influence of Interim Storage of Plutonium; A. Decressin, E. vanden Bemden. 2: Safeguards. 5. Security and Safeguards Aspects of Nuclear Material Handling in Russia; G.M. Pshakin, A.N. Tuzov. 6. Security and Safeguards Aspects of Plutonium Facilities in BNFL, UK; R. Howsley. 7. A Perspective on Safeguarding and Monitoring Excess Military Plutonium; W.G. Sutcliffe. 3: MOX Fuel Use. 8. Plutonium Burning in CANDU; P.G. Boczar, S. Kupca, P.J. Fehrenbach, A.R. Dastur. 9. The Safety Criteria and VVER Core Modification for Weapon Plutonium Utilization; I.K. Levina, V.V. Saprykin, A.G. Morozov. 10. A Plutonium-Fueled PWR 2000; P. Barbrault. 11. Potential for Use of All-MOX Fuel in Existing and Evolutionary/Advanced LWRs in the United States; C.E. Walter. 12. Use of Mixed Oxide Fuel in Existing Light Water Reactors in Germany; W. Thomas. 13. Japanese Nuclear Fuel Recycle: Plutonium Utilization Policy; T. Yamano. 14. Use of Plutonium in the UK; P. Wilcox. 15. MOX Fuel Utilization in Existing German LWRs: Design and Safety Aspects, Core Performance, and Irradiation Experience; G.J. Schlosser. 16. Development of Fast Reactor Core for Weapons Grade Plutonium Utilization; I.Y. Krivitski, V.I. Matveev. 17. Irradiation Experience and Post-Irradiation Examination Results for MOX Pellet Fuel of Fast Reactors; L. Zabudko, L. Moseev, L. Mamaev, S. Porollo. 4: MOX Fuel Fabrication. 18. Commercial MOX Fuel Fabrication and Irradiation Experience in Belgium; Y. Vanderborck, D. Haas, P. Deramaix, A. Vandergheynst. 19. Plutonium Utilization Experience in Japan; K. Kaneda. 20. Development and Fabrication Experience of MOX Fuel in the UK; K. Alldred. 21. Manufacturing Experience on Pelletized Mixed Oxide (MOX) Fuel for Fast Reactors; S. Antipov, V. Astafiev, L. Borisov, T. Menshikova, F. Reshetnikov, V. Revjakin, B. Zakharkin. 22. MOX Fuel Technology and MOX Performance in Germany; Plutonium Handling Experience; J. Krellmann. 23. MOX in France: Domestic Programme and MELOX Plant; J.-L. Nigon, C. Golinelli. 24. Experience on Development and Production of Vibropac MOX Fuel for Fast Reactors; A.A. Mayorshin, O.V. Skiba, V.A. Tzykanov. 25. Thermal and Fast MOX-Fuel from One Plant: Advantages and Limitations; W. Stoll. 5: Summary of Workshop Presentations. 6: NATO Workshop Summary Evaluation. Index.

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